2CAN060502, Cycle 18 Startup Report - Arkansas Nuclear One, Unit 2

Cycle 18 Startup Report - Arkansas Nuclear One, Unit 2

ML051660407
Person / Time
Site:	Arkansas Nuclear
Issue date:	06/11/2005
From:	James D Entergy Operations
To:	Document Control Desk, Office of Nuclear Reactor Regulation
References
2CAN060502
Download: ML051660407 (26)

Text

4, Entergy Entergy Operations, Inc.

1448 S.R. 333 Russeliville, AR 72802 Tel 479-858-4888 Dale E. James Manager Licensing - ANO 2CAN060502 June 11,2005 U.S. Nuclear Regulatory Commission Attn: Document Control Desk Washington, DC 20555

SUBJECT:

ANO-2 Cycle 18 Startup Report.

Arkansas Nuclear One, Unit 2 Docket No. 50-368 License No. NPF-6

Dear Sir or Madam:

Attached is the Arkansas Nuclear One, Unit 2 (ANO-2) Cycle 18 Startup report pursuant to ANO-2 Technical Requirements Manual Section 6.9.1.1. This section requires submittal of such a report following installation of fuel that has a different design. Cycle 18 is the first cycle at ANO-2 to be refueled with zirconium diboride (ZrB2 ) as the burnable poison in the fuel assemblies. The unit achieved criticality on April 10, 2005, following the 2R17 refueling outage.

Should you have any questions, please contact David Bice at 479-858-5338.

EJ/db Attaclnent: ANO-2 Cycle 18 Startup Report 4-flat C

II 2CAN060502 Page 2 of 2 cc: Dr. Bruce S. Mallett Regional Administrator U. S. Nuclear Regulatory Commission Region IV 611 Ryan Plaza Drive, Suite 400 Arlington, TX 76011-8064 NRC Senior Resident Inspector Arkansas Nuclear One P.O. Box 310 London, AR 72847 U. S. Nuclear Regulatory Commission Attn: Mr. Drew G. Holland MS O-7D1 Washington, DC 20555-0001 Mr. Bernard R. Bevill Director Division of Radiation Control and Emergency Management Arkansas Department of Health 4815 West Markham Street Little Rock, AR 72205

Attachment to 2CAN060502 ANO-2 Cycie 18 Startup Report

Attachment to 2CAN060502 Page 2 of 24 ANO-2 Cycle 18 Startup Report ABSTRACT This report summarizes the results of the startup physics test program. Results of these activities verify the Cycle 18 nuclear design calculations and demonstrate adequate conservatism in core performance with respect to the Arkansas Nuclear One, Unit 2 (ANO-2)

Safety Analysis Report (SAR), Technical Specifications (TSs), Technical Requirements Manual (TRM), and the Cycle 18 Reload Safety Evaluation. Cycle 18 achieved initial criticality on April 10, 2005.

Attachment to 2CAN060502 Page 3 of 24 TABLE OF CONTENTS Paae

1.0 INTRODUCTION

............................................................ 4 2.0 REACTOR CORE DESCRIPTION .........................  :.4 2.1 Loading Pattern and Assembly Bumup .................................................... 4 2.2 Incore Instrumentation (ICI) Locations ..................................................... 5 2.3 Verification of Core Loading ............................................................. 5 3.0 PRECRITICAL TESTS ............................................................ 5 3.1 Control Element Assembly (CEA) Drop Time Testing .............................. 5 4.0 LOW POWER PHYSICS TESTING ............................................................. 6 4.1 Initial Criticality ............................................................. 6 4.2 Critical Boron Concentration ............................................................. 6 4.3 CEA Reactivity Worth ............................................................ 6 4.4 Temperature Reactivity Coefficient .......................................................... 7 5.0 POWER ASCENSION TESTING ............................................................ 8 5.1 Reactor Coolant System (RCS) Flow Rate .............................................. 8 5.2 Core Power Distribution .................. ..................................... 8 5.2.1 29% Power Test Plateau Results ................................................ 8 5.2.2 65% Power Test Plateau Results ................................................ 9 5.2.3 100% Power Test Plateau Results .............................................. 10 5.3 Shape Annealing Matrix (SAM) and Boundary Point Power Correlation Coefficient (BPPCC) Measurement ...................... ................. 11.

5.4 Planar Radial Peaking Factor (RPF) Verification ................................... 11 5.5 Temperature Reactivity Coefficient ..................................................... 12

6.0 CONCLUSION

S .......... 12

7.0 REFERENCES

........................................................... 13 8.0 FIGURES Figure 1 Cycle 18 Core Loading ........................................ 14 Figure 2 Integral Burnable Poison Shim and Enrichment Zoning Patterns for Batch X Fuel Assemblies .15 Figure 3 Cycle 18 Fuel Management Scheme .......................... 16 Figure 4 BOC Assembly Average Burnup and Initial Enrichment Distribution ........ .... 17 Figure 5 ICI Locations ........................................................ 18 Figure 6 GETARP Output for the 29% Power Plateau ................................................ 19 Figure 7 GETARP Output for the 65% Power Plateau ................................................ 21 Figure 8 GETARP Output for the 100% Power Plateau .............................................. 23

Attachment to 2CAN060502 Page 4 of 24

1.0 INTRODUCTION

This report summarizes the results of the ANO-2 Cycle 18 startup physics test program. The startup physics test program consisted of a series of tests performed at various stages, including prior to initial criticality, low power physics testing (LPPT), and during power ascension.

The objective of these tests were (a)to demonstrate that during reactor operation the measured core physics parameters would be within the assumptions of the SAR accident analyses (Reference 7.1), within the limitations of the plant TSs (Reference 7.2), and within the limitations of the Cycle 18 reload safety evaluation (References 7.3 and 7.4), (b) to verify the nuclear design calculations, and (c) to provide the bases for validation of database and addressable constants in the core protection calculators (CPCs) and the core operating limit supervisory system (COLSS). Specifically, shape annealing matrix (SAM) elements installed in each channel of the CPCs are determined and the all rods out (ARO) planar radial peaking factor (RPF) is verified and conservatively adjusted in the CPCs and COLSS during power ascension.

Section 2 of this report provides a brief description of the reactor core. Section 3 discusses the pre-critical control element assembly (CEA) drop time test. In section 4, initial criticality and the low power physics tests are presented. Section 5 describes the power ascension tests, which include a reactor coolant system (RCS) flow rate determination, core power distribution measurements, the SAM determination, planar RPF verification, azimuthal power tilt verification, and a temperature reactivity coefficient measurement. The conclusions of this report are given in Section 6. Section 7 lists the references cited in this report.

2.0 REACTOR CORE DESCRIPTION The design of the ANO-2 Cycle 18 core includes using zirconium diboride (ZrB 2) as an integral fuel burnable absorber (IFBA). Zirconium diboride pellet coating replaces Erbia as the poison in the fuel assemblies. The ZrB2 rods have an eight (8) inch axial blanket (e.g., poison cutback) consisting of fully enriched annular pellets. The term 'fully enriched" means that the annular pellets have the same enrichment as the solid pellets in that rod. All fresh rods utilize ZIRLO fuel cladding material.

The 84 new fuel assemblies designated as Batch X were loaded with fuel rod enrichments as high as 4.21 w/o U-235 and a nominal B-10 loading of 3.14 mg/in in the ZrB 2 IFBA rods. In addition, 5 Batch U and 88 Batch W assemblies were loaded into the Cycle 18 core (Reference 7.3).

The mechanical design bases have not changed since the original fuel design. The designs and manufacturing processes for the grid cages and the upper end fitting were modified for the Batch X fuel bundle assembly design. This is a manufacturing process change and does not impact the mechanical design bases. All Batch X fuel rods use ZIRLO cladding material instead of Zircaloy-4 cladding (Reference 7.3).

2.1 Loading Pattern and Assembly Burnup Attached Figures 1 through 4, taken from the ANO-2 Cycle 18 Reload Analysis Report (RAR),

give the loading pattern and beginning of cycle (BOC) assembly average design burnups.

Attachment to 2CAN060502 Page 5 of 24 2.2 In-core Instrumentation (ICI) Locations The ICI design consists of 42 fixed ICI assemblies inserted into the center guide tube of 42 fuel assemblies. ICI locations are identified in Figure 5. Each ICI assembly contains 5 self-powered rhodium detectors and one core exit thermocouple (CET). None of the 42 ICI assemblies were replaced during 2R17 prior to the Cycle 18 startup. During power ascension, at least 190 of 210 possible detectors were operable.

2.3 Verification of Core Loading After the reactor core was loaded, core mapping was performed using an underwater television camera and monitor. This core mapping operation verified that the core was correctly loaded.

Core mapping was performed by the reactor engineering organization. The core mapping operation included a comparison of the identification numbers on the fuel assemblies, CEA configuration, and fuel assembly orientation against the design configuration.

3.0 PRECRITICAL TESTS 3.1 Control Element Assembly (CEA) Drop Time Testing This testing verifies that the drop time of all CEAs are in accordance with the surveillance requirements of ANO-2 TS 3.1.3.4. The method used by this test involves special control element assembly calculator (CEAC) software (CEA Drop Time Test, or CDTT software), which allows the measurement of all CEAs simultaneously. After the establishment of hot, full flow RCS conditions (i.e., greater than 525 OF with four reactor coolant pumps operating) and with the RCS boron concentration at a sufficient level to keep the reactor adequately shutdown during the test, all CEAs are withdrawn to the full out position. The CDTT software is then loaded into one of the CEAC channels and initiated. The software transmits a large penalty factor to each of the CPC channels, thereby initiating a reactor trip. The CDTT software records CEA positions every 50 milliseconds (msec) during the drop. Data output from the CDTT software is adjusted for holding coil delay'time and used to verify that drop time limits are satisfied.

From TS 3.1.3.4, the maximum individual and average 90% insertion times required for all CEAs are:

Individual Limit 3.5 seconds Average Limit :-3.2 seconds A 50 msec allowance is used for measurement uncertainty.'

All CEAs passed a limit of 3.45 seconds (TS limit minus 0.05 seconds). The slowest drop time was 3.350 seconds (CEA #80). The average CEA drop time was 2.956 seconds; which passed an average limit of 3.15 seconds (TS average limit minus 0.05 seconds).

In addition, ANO-2 utilizes the CEA drop time testing data as a CEA coupling check. If measured and expected drop times differ by more than 0.1 seconds for a CEA, then an additional review of drop characteristics (i.e., slowdown in the dashpot region, presence or

Attachment to 2CAN060502 Page 6 of 24 absence of 'bounce") is performed to determine the condition of the CEA. Expected drop times are obtained from historical data. If CEAs remain suspect after this further review, additional CEA coupling data may be taken during low power physics testing by exercising the suspect CEAs individually and monitoring the reactivity trace behavior on a reactimeter. This provides a final confirmation that any suspect CEA is coupled. For Cycle 18, all CEAs were determined to be coupled based on meeting expected drop times or review of drop characteristics.

4.0 LOW POWER PHYSICS TESTING 4.1 Initial Criticality ANO-2 normally withdraws CEAs to criticality. Shutdown Banks A and B are withdrawn and the RCS is then diluted to an estimated critical boron concentration corresponding to the desired critical CEA position. For Cycle 18, the estimated critical position was Group P at 138.4 inches withdrawn based on a measured RCS boron concentration of 1541 parts-per-million (ppm) prior to starting the approach to criticality. For Cycle 18, actual criticality was achieved with Group P at 100 inches withdrawn.

4.2 Critical Boron Concentration This test procedure specifies that the controlling group (Group P) be withdrawn from near fully withdrawn (< 75 pcm inserted reactivity) to fully withdrawn. As a pre-requisite, multiple RCS boron samples are obtained and compared to average to verify reactivity equilibrium. The residual worth of Group P is determined using a reactimeter. The average RCS boron sample is corrected for the residual Group P worth to determine the ARO critical boron concentration (CBC). For Cycle 18, the ARO CBC was predicted to be 1575.0 ppm (per Westinghouse, fuel vendor). The measured ARO CBC was 1591.8 ppm. The acceptance criteria is +/- 100 ppm difference between measured and predicted. Therefore, the -16.8 ppm difference for Cycle 18 was well within the acceptance criteria limit.

Using the measured ARO CBC, a shutdown margin calculation is performed assuming CEAs at the Zero Power Insertion Limits (ZPIL). The calculated shutdown margin is verified to be within the TS 3.1.1.1 / Core Operating Limits Report (COLR) limit. For Cycle 18, the calculated shutdown margin assuming CEAs at the ZPIL is -6.529 %Ak/k. This satisfies the TS 3.1.1.1 /

COLR requirement to have at least -5.5 %Ak/k shutdown margin.

4.3 CEA Reactivity Worth ANO-2 utilizes the CEA exchange method to determine the CEA reactivity worth. For Cycle 18, Shutdown Bank B was used as the Reference Group. The worth of the Reference Group is obtained by exchanging CEA insertion with dilution of the RCS at a continuous dilution rate of approximately 88 gpm. This provides both a total worth and an integral worth curve for the Reference Group. The measured worth of Bank B was 1708.98 pcm versus a predicted worth of 1793.90 pcm. The acceptance criteria is +/- 10%. Therefore, the 5.0% difference for Cycle 18 was well within the acceptance criteria.

The remaining CEA banks (or groups) are combined into test groups. These test groups are exchanged with the Reference Group. The final position of the Reference Group with the test group fully inserted and the Reference Group integral worth curve are used to determine the

Attachment to 2CAN060502 Page 7 of 24 test group worth. For Cycle 18, the four test groups were Banks 2+6, Banks P+4, Banks A+5, and Banks 1+3. The results are listed below in Table 4.3-1. All test groups were well within the acceptance criteria limits.

The total measured CEA worth was 5893.62 pcm versus a total predicted worth of 6067.90 pcm. The acceptance criterion for total CEA worth is +/- 10%. Therefore, the 2.96%

difference for Cycle 18 was well within the acceptance criteria limit.

TABLE 4.3-1 Measured Predicted Acceptance Test Group pcm pcm Criteria  %(P-M)/M Banks 2+6 955.72 984.10 +/- 15% 2.97 Banks P+4 967.61 1022.20 +/- 15% 5.64 Banks A+5 1128.50 1127.60 +/- 15% -0.08 Banks 1+3 1132.81 1140.10 +/- 15% 0.64 4.4 Temperature Reactivity Coefficient The isothermal temperature coefficient (ITC) is measured at approximately the ARO configuration. The average RCS temperature is varied by first increasing and then decreasing temperature by about 5 OF. The change in reactivity is determined using the reactimeter. The acceptance criterion states that the measured value shall not differ from the predicted value by more than i 0.3 x 10-2 %AkIk/ 0F.

The moderator temperature coefficient (MTC) of reactivity is calculated in conjunction with the ITC measurement. After the ITC has been measured, a predicted value of fuel temperature coefficient (FTC) of reactivity is subtracted to obtain the MTC. The MTC value must be less positive than + 0.5 x 10.2 %Ak/k/0F when power is

• 70% and less positive than 0.0 %Ak/k/OF when power is > 70% (Reference 7.2). The MTC must also be within the limits of the COLR for the current cycle (Reference 7.4). The measured MTC shall be extrapolated as necessary for comparison with the COLR. The extrapolated value shall be within the limits of the COLR for the current cycle.

For Cycle 18, the zero power MTC positive limit is + 0.50 x 10-2 %Ak/k/OF which decreases linearly with power to + 0.05 x 10-2 %Ak/k/OF at 50% power. The limit decreases linearly with power to 0.0 x 10.2 %Ak/k/OF at 60% power. At 100% power, the MTC upper limit is

- 0.2 x 10-2 %AkWkI 0F. The lower MTC limit (i.e., most negative) for all power levels is

- 3.8 x 10-2 %Ak/k/OF (Reference 7.4).

During low power physics testing for Cycle 18, the measured ITC was - 0.2940 x 10-2 %Ak/k/°F versus a predicted ITC value of - 0.2903 x 10.2 %Ak/k/0F. Therefore, the 0.0037 x 10-2 %Ak/k/OF difference was well within the +/- 0.3 x 10-2 %Ak/kI0F acceptance criteria limit.

Attachment to 2CAN060502 Page 8 of 24 The measured MTC at zero power was extrapolated to 50% power in order to compare to the COLR limit. The measured MTC is linearly extrapolated using predicted MTCs at zero and 100% power. The extrapolated MTC at 50% 'power was - 0.8886 x 10.2 %Ak/k/OF versus an upper (or positive) COLR limit of + 0.05 x 10.2 %Ak/k/OF at 50% power. The measured MTC at zero power was extrapolated to 100% power to compare to the COLR limit. The extrapolated MTC at 100% power was - 1.6531 x 1O02 %Ak/kIOF versus an upper (or positive) COLR limit of

- 0.2 x 10.2 %Ak/k/OF and a negative COLR limit of - 3.8 x 10.2 %Ak/k/OF at 100% power.

Therefore, the extrapolated MTC was in compliance with the COLR limits.

5.0 POWER ASCENSION TESTING 5.1 Reactor Coolant System (RCS) Flow Rate At the 65% power test plateau, the RCS flow rate was determined by calorimetric methods at steady state conditions in accordance with ANO-2 TS Table 4.3-1, Item 10, Note 8. The acceptance criterion requires the measured RCS flow rate to be at least 3% greater than the design flow rate of 120.4 x 106 lbm/hr to account for measurement uncertainties. The RCS flow rate determined calorimetrically was 6.58% greater than the required design flow rate, which satisfies the acceptance criteria for Cycle 18. The COLSS & CPC calculated RCS flow rates were verified to be conservative with respect to the calorimetric flow rate and the CPCs were verified conservative with respect to COLSS. No adjustments to COLSS and CPC calculated flow were made.

5.2 Core Power Distribution 5.2.1 29% Power Test Plateau Results Core power distribution data using fixed in-core neutron detectors is used to verify proper core loading and consistency between as-built and engineering design models. The first power distribution measurement is performed after the turbine is synchronized and prior to exceeding 30% power. The objective of this measurement is primarily to identify any fuel misloading that results in asymmetries or deviations from the reactor physics design. Because of the decreased signal-to-noise ratio at low powers and the absence of xenon stability requirements, radial and azimuthal symmetry criteria are emphasized, whereas pointwise absolute statistical acceptance criteria are relaxed. A core power distribution map at 29% power is given in Figure 6. The acceptance criteria at 29% follow:

a. For a predicted relative power density (RPD) < 0.9, the measured and predicted relative power density values shall agree within +/- 0.1 RPD units.

b. For a predicted RPD 2 0.9, the measured and predicted RPD values shall agree within i 10%.

c. The power in each operable detector shall be within +/- 10% of the average power in its symmetric detector group.

d. The vector tilt shall be less than 3%.

Attachment to 2CAN060502 Page 9 of 24 The acceptance criteria stated in a, b, and c above were met for all 177 locations and all operable detectors (195 operable out of a possible 210). From Figure 6, the maximum percent difference for a predicted RPD 2 0.9 was -3.96% (predicted RPD of 1.261 versus measured RPD of 1.21 1). The largest percent difference for an operable in-core detector relative to the average power in its symmetric group was 9.13%. The vector tilt was measured to be 2.13%;

therefore, the acceptance criterion stated in item d above was met.

5.2.2 65% Power Test Plateau Results At the intermediate power plateau of approximately 65% power, a core power distribution analysis is performed to again verify proper fuel loading and consistency with design predictions. The acceptance criteria at the intermediate power analysis follow:

a. The measured radial power distribution is compared to the predicted power-distribution by calculating the root mean square (RMS) deviation from predictions of the RPD for each of the 177 fuel assemblies. This RMS error may not exceed 5%.

b. The measured radial power distribution is additionally compared to the predicted power distribution using a box-by-box comparison of the RPD for each of the 177 fuel assemblies. For a predicted RPD 2 0.9, the measured and predicted RPD values shall agree within +/- 10%.

c. For a predicted RPD < 0.9, the measured and predicted RPD values shall agree within i 15%.

d. The measured axial power distribution is also compared to the predicted axial power distribution. The acceptance criterion states the RMS error between the measured axial power distribution and the predicted axial power distribution shall not exceed 5%.

e. The measured values of total planar RPF (F,y,), total integrated RPF (Fr), core average axial peak (F.), and 3-D power peak (Fq) are compared to predicted values.. The acceptance criteria state that the measured values:

Fxy, Fr, Fz, Fq shall be within +/-t 10% of the predicted values, and that COLSS and CPC constants shall be adjusted to appropriately reflect the measured values.

All of the acceptance criteria stated in a through e above were met for Cycle 18.

TABLE 5.2.2-1 PEAKING PARAMETER COMPARISON PARAMETER lMEASURED I PREDICTED I % DIFFERENCE*

Fogy _ 1.5551 . 1.4800 5.07 Fr 1.4263 1.4100 1.15 F,_ 1.1395 1.1100 2.66 Fq 1.6446 1.6000 2.79

• % Difference = %(M-P)/P obtained from GETARP output (Figure 7)

Attachment to 2CAN060502 Page 10 of 24 Calculated RMS values were:

RADIAL = 2.0236 AXIAL = 4.0553 A RPD map for the 65% power test plateau is given in Figure 7. The maximum percent difference for a predicted RPD 2 0.9 was 4.00% (predicted RPD of 1.160 versus measured RPD of 1.206).

5.2.3 100% Power Test Plateau Results The final core power distribution analysis is performed with equilibrium xenon at approximately 100% power. At this plateau, axial and radial power distributions are compared to design predictions as a final verification that the core is operating in a manner consistent with its design within the associated design uncertainties. The acceptance criteria are the same as those for the intermediate power distribution analysis stated in 5.2.2.a through 5.2.2.e above. The acceptance criteria stated in 5.2.2.a through 5.2.2.e for the 100% power test plateau Were met for Cycle 18.

The measured Fq was 10.11% greater than predictions. Per Section 4.5.4 of Reference 7.1, an evaluation of this condition was performed by the fuel vendor. The evaluation concluded that the applicable neutronics model, as well as the safety and setpoints analyses for the cycle, remained valid with the larger than normal Fq deviation. This evaluation was presented to the On-Site Safety Review Committee (OSRC). The OSRC concurred with the results of the evaluation.

TABLE 5.2.3-1

[ PEAKING PARAMETER COMPARISON l PARAMETER MEASURED PREDICTED  % DIFFERENCE*

Fxy1.5244 1.4700 3.70 F, 1.4078 1.3900 1.28 F, 1.1053 1.0700 3.30 Fq 1.7067 1.5500 10.11

• % Difference = %(M-P)/P obtained from GETARP output (Figure 8)

Calculated RMS values were:

RADIAL = 2.3774 AXIAL = 4.7633 A relative power density (RPD) map for the 100% power test plateau is given in Figure 8. The maximum % difference for a predicted RPD 2 0.9 was 4.99% (predicted RPD of 1.195 versus measured RPD of 1.255).

Attachment to 2CAN060502 Page 11 of 24 5.3 Shape Annealina Matrix (SAM) and Boundary Point Power Correlation Coefficient (BPPCC) Measurement The CPCs, part of the reactor protection system, use excore neutron flux detector signals to infer the axial distribution of reactor power. The algorithm, which infers the core power distribution from the excore signals, includes an adjustment for the non-uniform transport of neutrons between the core and the excore detectors. This adjustment is provided by the SAM.

The ANO-2 TSs require measurement and installation of appropriate SAM elements and associated BPPCCs after each refueling or verification of cycle independent SAM (CISAM) elements for each channel of the CPCs prior to exceeding 70% power. For Cycle 18, new SAM and BPPCC elements were measured.

There were minor complications with the SAM measurement. Specifically, the test matrix values for some of the CPC channels were not within acceptance criteria. The primary purpose of comparing a test matrix value (TMV) to acceptance criteria is to identify inconsistencies in data used to calculate the SAM and BPPCC elements. The ultimate criteria for judging the acceptability of SAM and BPPCC elements is the criteria on RMS error, which was satisfied for all four CPC channels at 65% full power. The TMV acceptance criterion was based on early analyses (circa 1975) of the sensitivity of CPC power measurement uncertainties to varying TMVs. In accordance with Section 4.5.4 of Reference 7.1, an evaluation of the failure to satisfy the TMV criteria was performed with the assistance of the fuel vendor. The evaluation concluded that the acceptance criteria for the TMV should be revised and that the measured SAM and BPPCC elements were acceptable as long as an additional penalty was applied to CPC addressable uncertainty constants BERR1 and BERR3 (power measurement uncertainty factors used in the Departure from Nucleate Boiling Ratio and Local Power Density calculations, respectively). The evaluation also recommended raising power to approximately 90% while collecting additional data for further evaluation. The evaluation was presented to the.OSRC and they concurred with the resolution. The SAM elements and BPPCCs were installed and power was raised from -65% to 90%. Following power ascension to 90%, further evaluations concluded that the additional penalties applied to CPC addressable constants BERR1 and BERR3 were no longer necessary. This further evaluation was also presented to the OSRC and concurred with. The additional penalties applied to BERR1 and BERR3 were subsequently removed.

5.4 Planar Radial Peaking Factor (RPF) Verification At the 65% power test plateau, the RPF for the ARO configuration was measured using in-core detector data and the CECOR computer code. The measured ARO F,' was 1.5577. The planar RPF multiplier corresponding to the ARO condition in CPCs (ARM1) addressable constant and the similar addressable constant (AB1 (01)) in COLSS were appropriately and conservatively adjusted as a result of this measurement prior to the plant increasing power above 70%. For Cycle 18, adjustments for other CEA configurations were not required.

For ANO-2, the CEA shadowing factors are not measured. The CPC database and addressable constants include allowances for using predicted CEA shadowing factors.

Attachment to 2CAN060502 Page 12 of 24 6.6 Temperature Reactivity Coefficient A moderator and isothermal temperature coefficient measurement was performed at 100%.

During the ITC and MTC measurement, turbine load is used to increase RCS average temperature, which decreases reactor power, and then to decrease RCS average temperature, which increases reactor power. This manipulation yields a ratio of RCS temperature change to reactor power change. Using a predicted power coefficient (PC) with the measured average ratio, an ITC is inferred. Using a predicted FTC with the inferred ITC yields an MTC.

Acceptance criteria state that the difference between the predicted and inferred ITC shall be less than 0.3 x 104 Ak/k/JF. For Cycle 18, the MTC shall be less negative than

- 3.8 x 104 &k/k/0F but less positive than the curve in the Cycle 18 COLR.

For Cycle 18, the ITC and MTC passed the acceptance criteria. The measured ITC was

- 1.20 x 10' Ak/k/ 0F versus a predicted ITC of -1.34 x 104 Ak/k/0F. The difference was 0.14 x 104 Ak/k/ 0F which was within the +/- 0.3 acceptance criteria. The measured MTC was

- 1.04 x 10- Ak/k/OF and within COLR limits.

In addition, the measured MTC was extrapolated to 100% power and predicted peak boron concentration to verify the MTC remains less than 0.0 Ak/k/ 0F and within COLR limits. The extrapolated value is - 0.89 x 10- AkWJOF. For Cycle 18 only, the MTC will be measured at the peak boron concentration to confirm the predictions.

The measured MTC was also extrapolated using predicted AITC/APPM to 100% power and through end of cycle conditions. This extrapolation indicated that the limiting boron concentration for maintaining COLR compliance can not be physically achieved (i.e., negative boron concentration) during the cycle, verifying that the negative MTC limit of - 3.8 x 10' Ak/k/OF will not be exceeded during Cycle 18.

6.0 CONCLUSION

S Based upon analysis of the startup physics test results, it is concluded that the measured core parameters verify the Cycle 18 nuclear design calculations and the proper loading of the core.

All test values were found to be acceptable with respect to limits and requirements contained within the ANO-2 SAR and TSs. These results include:

CEA Drop Times Critical Boron Concentrations CEA Reactivity Worths Temperature Reactivity Coefficients (during LPPT and at power)

RCS Flow Rate by calorimetric measurement Core Power Distributions at 29%, 65%, and 100% power test plateaus SAM Measurement Planar RPF Verification The above test results demonstrate adequate conservatism in the Cycle 18 core performance with respect to the ANO-2 SAR, TSs, TRM, Cycle 18 COLR, Cycle 18 RAR, and Cycle 18 reload safety evaluations.

Attachment to 2CAN060502 Page 13 of 24

7.0 REFERENCES

7.1 ANO-2 Safety Analysis Report (SAR), Section 4.5, Startup Program and Section 15, Accident Analysis 7.2 ANO-2 Technical Specifications 7.3 ANO-2 Cycle 18 Reload Analysis Report (RAR), CALC-A2-NE-2004-000 7.4 ANO-2 Cycle 18 Core Operating Limits Report (COLR), CALC-A2-NE-2004-001 7.5 ANO-2 Procedure 2302.003, Change 011-02-0, Determination of CEA Group Worths by Exchange, 4/10/2005 7.6 ANO-2 Procedure 2302.009, Change 022-00-0, Moderator Temperature Coefficient at Power, 4/28/2005 7.7 ANO-2 Procedure 2302.021, Change 021-00-0, Sequence for Low Power Physics Testing Following Refueling, 4/10/2005 7.8 ANO-2 Procedure 2302.022, Change 013-01-0, Initial Criticality Following Refueling, 4/10/2005 7.9 ANO-2 Procedure 2302.023, Change 009-00-0, Low Power Physics Base Power Level Determination, 4/10/2005 7.10 ANO-2 Procedure 2302.026, Change 012-00-0, Isothermal Temperature Coefficient Measurement, 4/10/2005 7.11 ANO-2 Procedure 2302.028, Change 011-00-0, Determination of Critical Boron Concentration and Inverse Boron Worth, 4/10/2005 7.12 ANO-2 Procedure 2302.034, Change 019-00-0, Power Ascension Testing Controlling Procedure, 5/6/2005 7.13 ANO-2 Procedure 2302.039, Change 012-01-0, Core Power Distribution Following Refueling, 4/12/2005, 4/13/2005 & 4/22/2005 7.14 ANO-2 Procedure 2302.046, Change 008-05-0, CEA Drop Time Test, 4/9/2005 7.15 ANO-2 Procedure 2302.057, Change 003-00-0, RCS Calorimetric Flowrate Calibration Using RCSFLOW Program, 4/13/2005 & 4/18/2005

Attachment to 2CAN060502 Page 14 of 24 FIGURE 1 Cycle 18 Core Loading Fuel Rods Number of per Assy Nominal Shim Fuel Rods Assembly Number of (not including Enrichment ZrB 2 Rods Loading (Including Number of Designation Assemblies ZrB 2 Rods) (wt% U-235) per Assy (ZrB2) ZrB 2 Rods) ZrB 2 Rods X1 16 184 28 4.21 3.81 240 2x 2944 832 3840 X2 8 176 4.21 8 2x 1472 64 12 3.81 40 2x 416 320 X3 12 164 4.21 20 2x 2208 240 12 3.81 40 2x 624 480 X4 36 136 4.21 48 2x 6624 1728 0 3.81 52 2x 1872 1872 X5 12 112 4.21 72 2x 2208 864 0 3.81 52 2x 624 624 Total 84 19824 6576 Fuel Rods Number of per Assy Nominal Shim Fuel Rods Assembly Number of (not including Enrichment Erbia Rods Loading (Including Number of Designation Assemblies Erbia Rods) (wt% U-235) per Assy (wt% Er203) Erbia Rods) Erbia Rods W16 152 4.54 0 - 2432 60 4.24 24 2.1 1344 384 W220 152 4.54 0 - 3040 36 4.24 48 2.1 1680 960 W38 136 4.54 0 - 10888 12 424 88 2.1 800 704 W4 44 128 4.54 0 - 5632 8 4.24 100 2.1 4752 4400 Total 88 20768 6448 U3136 4.17 0 - 5448 12 3.87 88 2.1 400 352 U4128 4.17 0 - 128 8 3.87 100 2.1 108 100 Total 5 1180 452 ZrBI GRAND 177 41772 6576 TOTAL Erbia 6900

Attachment to 2CAN060502 Page 15 of 24 FIGURE 2 Integral Burnable Poison Shim and Enrichment Zoning Patterns for Batch X Fuel Assemblies Xi (24 ZrBl Pins) X2 (48 ZrB2 Pins)

IKI_ . KLle_

I 1_x _I 1 m T= I1- I ilill EX _ll_

1SI _ _ I III X3 (60 ZrB2 Pins) X4 (100 ZrB2 Pins)

_HL-h Ekilc d Fuel Rod Law EulideI rUdl.R Mgt EhidinaZrD2 Roa Lcu YmHd aE z. Rod X5 (124 ZrB2 Pins)

Attachment to 2CAN060502 tI Page 16 of 24 FIGURE 3 Cycle 18 Fuel Management Scheme m33= u=m lxzfi= .s

= ..

mXX=QUWCCaD;}otrCUSC my =NmrbufYc&

1 2 3 W2 W4 14 F I*-*

11-2 4.

44-0

- - - I 14- 2 4 5 6 7 a

-W2 Wr4 Xi X2 X3

.1 07-2 1 35-3 I I 9 10 11 12 13 14 U3 xl:k X3 X4 W24 X4 04-2 20-2 15 16 17 18 3 20 21 15 16 x W 1 X4 13 X4 214 38-2 16-0 12-2 26-1 22 23 24; 25 26 27 28 W4 X3 RX4 W4 X5 WI X5 42 -1 33-0 06-3 29 30 31 32 33 34 35 36 W`2 Xi X4 -W3 X5 W4 X4 WI 23-2 31-2 18-0 10-3 37 38 39 40 41 42 43 44 W4 X2 W4 X4 WI X4 W2 W4 24-1 40 -2 :2 30-1 08 -2 28 -0 45 46 47 48 49 50 51 52 W4 33 X4 :W4 X5 WI Wn4 U4Mt 47-2 26-0' 10-2 49-0 28 -0

{1) U4 assembly relnserted from the spent fuel pool, discharged atthe erd oT Cycle 16

Attachment to 2CAN060502 Page 17 of 24 FIGURE 4 BOC Assembly Average Burnup and Initial Enrichment Distribution 55 - Batch Idener forAssen yrnn 1 W2 2 WA4 3 V'.

AssemmbAerage Burnup (MA ) , I, 22550 24E0D .24805

- Y - * - * - S -

4 W2 5 W4 6 Xi 7 X2 B X3 21600 .251W0 a G a Z.21 13.81 d.211 3.81 4.2113.61 9 .3 10 xi 11 '- X3 12 X4 13 W.., 1' X4 32E01 0 4 a 25100 0 42113.81 C42113.81 L.21 13-81 42113.81 15 ' 12 16 Xi 17 WI 18 X4 19 W3 20 X4 21 W.

21600 0 17800 0 2420o 0 24900 4.2113.81 4211381 .21 1381 22 W 23 X3 24 X4 25 W4 26 Xs 27 WI 28 X5

.4 25100 iD 0 4.249MO 0 19SO0 a 4.2113.61 42113.81 d.2113.81 4.2113.61 29 U2 32 Xi 31 X4 32 W3 33 X. 34 W4 35 X4 36 Wi 22510 0 O 2420 0 24000 0 17602

- 2113.81 42113.81 4.211381 - .2113.81 37 W4 33 X2 39 W, 40 X441 Wi1 2 X4 43 1'2 44 W.

24M0M 0 2510 0 1C 0 22300 25303

.2113.81 42113.51 d.2113.81 45 W4 46 X3 47 X4 48 W4 449 X5 53 WI 51 %W/452 U4 24830 a O 24900 a 17630 25300 25E02

- .2113.81 4.2113.81 - 42113.81 Batch XZrEF rods haYe annular pellets ki top &botom roo rm at tie rods nominal enrlchment

4 -  !

Attachment to 2CAN060502 Page 18 of 24 FIGURE 5 ICI Locations a - J K L N p 2 IM A I C D I .  !

aI I I I I II II 71 1.

I I* *

• I a .

I .- I*- --

t1 I I 1 . ^-

4. I I 2~-- -- a----a_ a. I 0 0 0 I I I I 21 A I

2 *..-.---I----O-. § _ X I I I i I . I I I I I oI J ---- 5

• I O .. O._

] 'I'o I~I 09I o 1 1' a I 1__ a _ 6 o

14 I 0 IAis Io _ _ _ I 0o14 _ _

0 Io__

17 _ _

0 I o 0 0 22

. 22-- 24 6 - 0 0 £) .,2 21 27I0 o0 D. I I 0 I 0

- 21S 0Ii 22 ) I 74 0 1,_ - _ O-0

_ O O _ - 4a _

I_ ,-

13 I___ __ ) _

0 0 0 41 _ -

I2

. 4 4 A3 4 .

'A

~.-

s - 0 DETECTOR AXIAL LEVEL LOCATIONS: J I 5O1TOM OF CORE JP3 MDDLZ OF CORE JJuS .TOP OF CORE

Attachment to 2CAN060502 Page 19 of 24 FIGURE 6 GETARP Output for the 29% Power Plateau G EMMETS TTTTTZTTT AASAA RRMRPPRR PpPVPPPVP 0 5 SSSS hT ASt AAtA 811 P 313 992 19 010 0c 0 *itzzm t Mm AAA AA RIPRRRUA RRR PP9P91 cor3sEE T!m A MA RM R M I9 VP9 C100 00001 ZELM 1 TIT AAA MA MR JIRA P9 P 0200000000 1 z . hT A AA "A FAR I'9NIP A VACGMMTO Ulpi#h DATAPW CC SM.A rl721 IM CARISM Cy AXIAL AMD MAOIAL" VIST31>48.

GIT77NP1 - ClTAI Vf ST 3ZEVS1O4 1 ICASUMD DATA lXSRACTID VK4. .2154x4.aSl PREDICTS D DATAZXTRACTSD TIKH e2pad.029 RZZATIV XADIAL V01MIDSISTRISCN COMPARTJM I RD3ICMT g J .419:t-30 .5411 .3305 .4420IfA3.-PMDICTKD2 tIAURSD It .448: .J135 .54t5 .444 t DIlM M --- 100.0 2-----

4D:mR t t2.14t .92 t 1.40 t 1.38, .44 t PtEDICTED t .453  : .477 I 1.105, 1.157 I 1.130 I 1.141 t 1.108 I .47 : .13

.473 .o50 s 1.083a 1.151 1.120 t 1.1429 1.074 t .646 4 .44t I 4.37 : -4.05 -1.97 -.51 t -.11 t -1.04 -3.00; -4.72 ; 2.40 4 ~ --.- 4--- -T-2--.477

• .477 1.122 1.201 1.e14 tI.0.15 t1.094 :1.155 1.202t1.123t .477t S .508 t 1.131 t 1.18 S .142 1.079 1.15 1.01 5 a 1.144 t 1.141 t 1.097 t .484

£ 6.55 : .82 a -1.24 t -. 44 -1.25 t -.04 1 -2.45 1 -2.10 1 -3.40 1 -2.36 1 2.22

.453 1.123: 1.261 i 1.194 I 1.082 i1.134 :1.041 1.135 I 1.082 1 .194 1 1.241 t 1.122 .453

.500 s 1.187 I 1.221 : 1.214 r 1.088 J 1.142 1:1.00 1.149 1 1.067 1 1.103 1.211 j 1.109 1 .470 1 110.31 2.90: -. 0231 1.4 , .57, .90 -. 05: 1.26: -1.40t -. 92 :-3.96 -. 16: 3.74 ;

• .678 1.202 1 1 1.194 I 1.011  : 1.047 1.164 t 1.117 1.142 11.047 t 1.051 : 1.194 11.201 t .477 t

.704 t 1.227 11.222 11.045 t 1.104 11.171.: 1.139 I 1.168 1.082 t 1.029 t 1.172 1.109 : .47 2.77: 2.11

• 2.32 t 1.29 t 3.44: .40 t 1.94 * .49 a1.39 : -2.080 -1.84 t -2.49 -1.48 i t.442 , 21.10 t 1.148  : 1.082 t 1.047 t 1.074 t 1.200 t 1.248 1 .197 t 1.014 t 1.07 1t.082 t 1.147 ' 1.105 .43I

.448 a 3.132 11.209 : 1.102 t 1.091 I1.093 t 1.231 t 1.245 t 1.212 t l.0O4 .051 t 1.013 1.148 1.07 S .437 1.30J 2. 18 3.52 1.83 1 2.64 l 1.81 2.9 : -. 26t 1.21 a-.00 -1.52 a -2.70 t-1.67i-3.05 s -. 45 s I.5311.141:11.@8:1.135u11.121 1.197 1.170 : 1.119 21.170 ,.200 1 .14 4 1.134 , 1.093 1 1.157 t .5301 I .583: 1.204 2 1.11 a 1.177 1.181 t 1.23 : 1.193 : 1.127 t 1.153 1.188 : .139 t 1.122 t 1.057 1.122 t .522 i t4.58 3.47:1.80: 3.172t 1.89: 3.50 t2.00 Y 7: i -. M8 t-.17: -2.14i -. 64 -3.27 -3.02 -1.40S

.54 a 1.130 : 1.155 a 1.041 a 1.117 : 1.248 1.11 t: 1.031 1.119 1.248 : 1.117 : 1.001 : 1.155

• 1.230 : .541

.54 a 1.148

• 1.171 a 1.077  :

1.150 ' 1.278 : 1.14 1.047 1.093 : 1.219 : 2.104 a 1.044 : 1.137 : 1.097 i .5133 1

4.41 a 1.72 : 1.35 a 1.48 3.80 : 2.28 2.33 a 1.57 -3.25 -2.30 : -.99 t -1.40 t -1.53 a -2.99 -1.SS a

.530 11.57 : 1.093 1.130 g 1.:14 : 1.200 : 1.170 a 1.119: 1.170 a 1.37 , 1.142 : 1.133 a 1.094 : 1.14 a .81

• t.547 a 1.16 : 1.09 : 1.149 t 1.10 t 1.240 1.5822 1.124 : 1.4S4 1.12 8 1.144 a 1.3a 12.0t2 : 1.131 : .524 3.23 1.04 : .22 a 2.S3 5 2.02 : 3.31 t 1.S2 5 .85 -1.41 : .05 : -1.42 a -. 22 5 -2.93 : -2.42 : -2.45 I.439 1.105 : 1:.17: 1:.082 : 1.047 ' 1.0X74a 1.7 : 1.240 1.200 .074 I 1.047 1.082 : 1.28 1.08 : .442 5 .159 : 3.110: 1.183 5 1.085 I I.01 1.083 r 1.220 : 1.238 1.19 a 1.073 : 1.044 1.057 1.158 1.072 : .410 a 4.49 1.00 : 1.37 : .32 a .81 : .91 : 1.85 : -. 71 :-.10 -. 11: -.24 a-2.33 -. 76 a -3.29 : -7.23

.677 1.201 1.194 t 1.01 t 1.047 I1.162  : 1.117 : 1.44 : 1.047 1 U101 r 1,  : 1.202 : .478 a .702 l.215 2 I 1.207 : 1.048 23.082 : 1.542 : 1.131 1 1.087 : 1.048 9 1.184 : 1.183 : .414 1 3.49 1.12: 1.11 -. 25 : 2.32 : .02 : 1.291 -. 40 : 1.90 : -.18 : -. 88 : -1.55 : -. 59

.45 : 1.122 : 1.241 I 1.184 : 1.082 : 1.135 :.1.041 : 3.134 : 1.082 : 1.194 : 1.261: 1.123 .453 a .487 1.143 1.247:1.204 1.074 :1.144 1.053 :1.137 1.049t :1.200 1.229 1.12: .479:

8.61 3.ta -1. C8 .97 t-.73; .99 -. 80 .11 -1.21, .32 -2.351 .44: 5.83;

• ------.--____________.._.----___.___.____---_--------_____-4------.

.477 : 1.123 : 1.202 r 1.1t : 11.004: 1.155 1.093 1.1t7 a 1.201 1122 : .477 t o.5001.120 1.1741 :1.149 1.045 1.144 1.060

• 1.141 a 1.164 : 1.105 S .493 4.84 I -.24 : -2.15 : -1.41 : -2.67 : -. 98 : -2.88 -2.20 a -2.83 a -1.51 32.42

.4533 .078 I1.108 : 1.161 1.130 : 1.157 : 1.105 a .4n : .453

.64 5 1.072  !.443 1.140 .1.106 1.130 : 3.043a .39 1 .-441 3.40 t -4.44 a -3.14 : -1.83 t -2.11 j -2.33 1 -3.77 : -5.46 a 1.78 1

.442 : .538 t .811 : .830 3.43a

.444 .538: .540: .527: .438:

.34 .22: -. 11 t .-. 57: -. "

Attachment to 2CAN060502 Page 20 of 24 FIGURE 6 GETARP Output for the 29% Power Plateau (continued)

RELATIVE IL POWER DISTRU=TIO CClP.IBW tlCC F 1D: WS I DlTREH=

1 .5540 .5542 .0429 2 .6790 .6317 -6.9601 3 .7910 .6994 -11.57S4 4 .8270 .7570 -8.4690 S .8430 -. 045 -4.5726 7 .e660 .8714 . 6180 e .8740 .8925 2.1214 9 .800 .9071 3.0904 10 .8840 .8164 3.6626 11 *8880 -: .S217 3.7963 12 .8910 .9244 3.7520 13 .S950 * .9257 3.4354 14 .s990 .9267 3.0826 15 .9030 .9282 2.7873 16 .90:0 .9307 2.5040 17 .91 0 . .9348 2.27n0 18 .9200 .9405 2.2280 19 .9280 .9478 2.1346 20 .9360 .9565 2.1929 21 .9440 .9663 2.3661 22 .9540 .9769 2.3971 23 .9650 .9877 2.3572 24 .9760 .9986 2.3197 25 .9900 - 1.0093 1.9495 26 1.0050 1.0196 1.4521 27 1.0210 1.0295 .8343 28 1.0310 1.0392 .4061 29 1.0400 1.0499 .0049 30 1.0590 1.0589 -. 0093 31 1.0700 , 1.0696 -. 0367 32 1.0810 1.0814 .0334 33 1.0920 1.0944 .2241 34 1.1040 1.2090 .4553 35 1.1150 1.1251 .9035 36 1.1250 1.1423 1.5411 37 1.1360- 1.1603 2.1394 38 1.1470 1.1782 2.7108 39 1.1580 - 1.1949 3.1976 40 1.1630 1.2092 3.5245 41 1.1790 - - 1.2194 3.4281 42 1.1eo 1.2240 3.0286 43 1.1950 1.2211 2.1834 44 1.1980 1.2090 2 .9183 45 1.1970 1.1961 -. 9142 46 1.2910 1.1508 -3.3747 47 1.1790 1.1021 -6.5236 48 1.1590 - 1.0391 -10.3451 49 1.1100 .9615 -13.3796 50 .9570 . e694 -9.1577 51 .7860 .7633 -2.8B20 PEAKIN PARMETER CO1ARISOZH PARAMETER MAf. - PRED2CTED % O D ZR. l MY 1.5619 1.5100 3.9023 %

PR 1.4392 1.4300 .6426 4 nE 1.2240 1.2000 1.9983 4 PQ 1.7827 1.7700 .7190 %

CALCULATD JM VALUES MDAL - 2.2059 AXIAL - . 4.286

)MASURED ASI . -. 1046 PRODICTD AJS1 - -. 1132 AMETANCE CRITERIA REPORT MASURIZD YElT WIHfIN PLUS OR ta"US 10.000' OF TUE PREDICTED VALUE.

I<ASURO WfMtS 'WITHIN PWMS OR HMtJS 10.000 i oF THE PREI D VALVE.

.SURD 8 1E.8 WITHIN PLWS OR bamS 10.000 % Or THE PREDICTED VALUE.

MASURZD 20 VAS WITHIN PLUS OR INUS 10.000 4 CT THE PREICTED VALUE.

PM ERROR ON AAL DI8TRXWTI0.W WAS LESS THAM OR EQUAL TO 5.000 t.

a ERRORCO RADIAL DISTRIBUTION WAS LESS TSAi OR EQAL TO s.000 4.

ALL PREDICT=D RADIAL POVERS LESS TAIAt 0.9 WEE WITHIN PLUS OR KINUS 15.000 S oF MASURD.

ALL PEDICTD RD1IAL PERS GREATEK THAN OR EQUAL TO 0.9 WE" WITHIN PLUS OX MINUS 10.000 % cr MEASURED.

ALL ACU PTA CRITERIA WERE MCS T*.

r s.

Attachment to 2CAN060502 Page 21 of 24 FIGURE 7 GETARP Output for the 65% Power Plateau GOOG00= iczczz TTTTTsTT n AA. MARSS8AAFJ mR PPPPPPPPP XCO G ZmmrZZ TTTTTx .TTM AAAAAA 3itIAMAR Pv vPPPVPPP G i m AAA AA A RRR RRR 9nP 9PF OCG G= m - TTm AAAAAAAAAA mMARMUM P FPP2P92p1 coo C: mI, t1 T AAAAAAAAAA RRFRRRM.5 PPPPPPPPP 0C0 000 m1 m? AAA A"A RA RRR 9PP

-  : : 05,E11 m 2 AAA AmA PRR 935 PPP 0o000 mz1M m T AAA A"A PPR R t8PP (TPA)

A PrOGAM TO ITRACT DATA PROW CCOG St"ARY rIMS rGA COwARISON Or AXIAL1 Apo RADIAL PONKR DIUSsUIICts.

Cl79n201 - C1TAAP FMA ,tT RVSI1 I WA9M8! DATA ZXTDACID rKFD: &2155zp.&01 18sDIC7m DATA 1xTxAc!c nmms A2D.068 RLATrII RADIAL KCWZDISTRS13TIC CCHPAAR3S3 s =ICTCD :D .451 :...54  : .55I *5S1  :.45:4 DEAB.-1IGICTseD)

ASRrD 1 a .448 .3 i . s .5441 .6433 t D I m -= _ ------ x 200.0 a  % DIIESR I -. 72 1 -1.96 1 -1.17 : -1.35 , -2.32 I P2RICbDT

.462 : .685 1.106 1 1.154 1.131 1.160 1 1.108 1 .486 ; .462

• .471 5 .652 :1.085 I 1.152 1 1.120 1 1.146 1 1.077 1 .453 1 .466 1 2.00 -4.75 -1.81 -. 36 j -. 8 -1.19 1-2.77 -4.800 .81:

a .484 1 1.114 1.182 :1.162 12.082 1 .15  : 1.0I2 2 1.143 1.193 1.115 1 .484*

s. 3 1.126: 1.1 31.1 62: .0 , 1.57 1.066 1.147 .165 J2.101 t .406 p 3.82 t 1.06 t -. 72; -. 02 t -1.08 .23 -2.34 -1.39 1 -2.33 : -1.29 1 .45;

+_-*--- @--------*--------*--------- --- U ---- - -------- ...... -----------------------

.452: 1.1123 .243, 1.186,1.080 11.234 1.062 t 1.136 1 .080 : 1.2185: .243: 1 .114 .A2O

.3 :1.15232 .21  : 1.205, 1.0 t1.146 i 1.063 :1.155: 1.049 1.181 1.214 1.111 .410:

6.71: 3.34 .62: 1.10 .531 .8 8 .123 1.71 -1.06 -. 37 -2.34 -. 281 1.81 .

.0681 1.193 aI.185, .e0s 1.070 11.141 1 2.117 u 1.159 1.069 1.050 1.166 1.1922 .S6S6

.416 :1.214 1.213: 1.060 : 1.103 : 1.172: 1.142 : 1.172 1.064: 1.033 :1.178 1.176, .668:

1.441 1.75 1 2.37 1 33.098 .84 : 2.23 : 1.11: 1.40 -1.43 i -. 47 1 -1.35 1 -2.261

.- -- - -- - - - -- - -- -- - -- .- -- - -- .- -- - - -.- - - - - - .-_-- -.- -- - -- - -- - - .- -- - -- - -- -- .-- -- -- - -- 4

.45  ;

1.108 1.263 1.001.0 t:1.074 : 1.16: 1.240 1.193 :1.074 1.070 1.080 1.162 :.106: .451:

.440 t 1.126 1.190 i 2.094 1.099 t1.083 h 1.232 1.247 1.217 1.070t 1.063 t1.060 1.160 t.078 .4381

-1.21 1 1.58 : 2.31 1 1.31 1 2.78 1 1.7981 3.00 J .57 S 2.0. 1 -. 39 1 -. 69 t -1.82 t -. e1 -2.56 t -2.89 8

.551: 1.160 : 1.092 S 1.136 : 1.159 1.183 1 1.166 J 1.117 1.166 5 1.16 .161 1.136 t 1.092 t 2 1.156 t .544

.563 s 1.206: 1.20  : 1.174 12.18s: 1.240 / 1.193 J 1.27 7 1.159 J 1.203 . 1.147 21.136 1.062 1.124 : .521 2.13: 4.00e 1.46: 3.34 2.25: 3.94 :2.355 .84: -. 59 : .40 -1.21 -. 01 5-2.74 -2.76 -4.14:

.554 1.1231 1.154 . 1.062 : 1.117 : 1.240 : 1.117 z 1.035 J 1.117  : 1.240 : 1.117 1.062 2 21.154 1.131 a .554 5 .564 1.150 : 1.170 5 1.015 1 1.140 1.270 1.145 : 1.046 1.077 j 1.222 a 1.115 i1.048 1 1.141 1 1.096 a .532 1.80 : 1.70 1.35  ; 1.21 : 3.84 3.11 .2.49 1.02 -3.61 ; -1.42 ; -. 22 5 -1.32 : -1.17 : -2.88 -3.94

.544 :1.16 t1.092  : 1.136 11.141 51.196 i 1.16 11.117 1.166 1.193lS31.1591.136: 11.092 t 1.160 .551 t t .546 1.16 : 1.094 : 1.168 s 1.189 t 1.242 : 1.184 t 1.126 : 1.153 3 1.201 I 1.1S0 l1.135 . 1.041 5 1.128 : .524 i

.35 1.16 .20 . 2.88, 2.39 23.844 2.37 , .5: -2.098 .4S -. 77 P -. 08 -2.83 -2.75: -4. 4 5 .451 1.104 : 1.162 t 1.0B0 j 1.070 1.074 t 1.193 1.240 : 1.196 t 1.074 a 1.068 5 1.080 : 1.163 : 1.108 a .454

.457 1.114 1.178 1.083 a 1.081 1.04 41.225 1.242 1.202 1.075 1.069 t1.056 1.156 1.072t .4105

2.33 .49: 1.41: .32 1.05t .97 t 2.68t .17 .53 .05 .00 -2.23 -. 61 -3.22 -7.088

.685 1.192 1.186 1.050 1.069 1.1595 1.117 11.161 t 1.070 : 1.050 t.1BS 1.193t .686Z

,.se a 1.209 1.204, 2 1.047 a 1.03 S 1.125 p 1.134 : 1.162 : 1.089, 1.047, 1.183 S 1.179 .471 1.84 t 1.39 t 1.54 t -. 27 t 2.24 t -.49 t 1.55 t .07 : 1.67 i -. 32 5 -. 18 : -1.18 : -2.14

.462 : 1.114 : 1.243 5 1.1285 1.080 5 1.136 : 1.062 s 1.136 5 1.080 , 1.186 : 1.243 : 1.115 : .462

.492 : 2.152 : 1.242 p 1.201 1: .074 1 1.150 : 1.053 : 31.42 : 1.067 : 1.192 1 2.223 : 1.219 : .475

6.42 3.41 -. 05t 1.38 -. 59 1.24 : -. 69 g .53 -1.17t .53 -1.65a .332 2.91:

+_ _____________ -.--~-_

_________ __----4----__--

• .484 1.115 1.193 1.163 ,1.092: 1.154 1.092 1.142 1.192 1.114 : .484 :

.497 1 1.119 1.177 t 1.151 1 1.045 s 1.145 s 1.061 1 1.142 1 1.165 s 1.102 .490 2.60 5 .35 , -1.34, -1.07 s -2.45 : -. 76, -2.84 -1.74 -2.22; -1.04 1.20, 4

.442 t .486 t 1.108 : 1.140 1 1.131 2 1.156  : 1.106 : .45: t .462

.470: .652 1.075 1.1308 1.106 1.129 t 1.045t .645 .441:

a 1.66 t -5.02 a -2.85 a -1.89 : -2.24 -2.34 1 -3.71, -4.20 -. 31 t .454 1- .551 1 .554 s .544 5 .451 1

• .443 5 .530 S .539 5 .526 : .437

-2.43 . -2.44 1 -2.753 -3.40 : -3.01

+ _ __ _^ l __ _ ___--___ _

Attachment to 2CAN060502 Page 22 of 24 sB*0DFEEC N- PRDCE FIGURE 7 GETARP Output for the 65% Power Plateau (continued)

RELATIVC AXIAL POWER Vt[TSVThPIIOK COW)ASO14 1 .6200 .6135 -1.0465 2 .7550 .6986 -7.4762 3.- .7724 -21.9320

.9110 .343 -9.3944 S .9240 .8651 -4.2085 g30 246 22 f22 7 .99410 .537 1.93545

• .9460 .9738 2.9334 9.9490 .9859 3.8935 10 .9500 .0918 4.4045 21 .9510 .9930 4.4249 12 .10 - .9909 4.2963 13 .5200 .9670 3.6709 24 .530 .9826 3.2040 15 .9570 2.5794 2.786 16 .9560 - .9759 2.0791 17 .9530 .9749 1.7633 I: .9610 .9753 1.5509 9 .9950 .9789 1.44289 15 .::I 976 .59 20 .9700 - .9393 1.4199 21 .7510 .9901 1.1478 22 .9a10 .99 1.6798 23 .9880 1.0055 1.7677 24 .950 1.0136 1.8704 25 1.00 .0215 21.7475 26 2.0160 2 .290 1.2790 27 210270 I.0359 1.620 29 .90350 1.0421 .6860 29 2.0420 2.0479 .5645 30 1.0480 91.0534 .5195 31 1.0550 2.91 .3897 32 1.0910 1.0652 .3950 33 1.0670 1.0720 .4703 34 1.0720 1.0798 .7278 35 1.0780 - 1.086 .9844 32 1.0930 1.0983 1.4155 37 1.0160 1.10:l 1.2938 38 1.0230 . 1.118 2.3640 39 1.0970 1.1122 2.8417 40 1.1020 1.1355 3.0410 41 1.1070 1 1395 2.9402 42 1.1100 1.0138 2.5965 43 1.1110 1.2131 .3S700 44 1.1090 1.7076 1.1168 45 1.0030 1.08925 -. 9480 46 1.0920 1.073 -3.1559 47 1.0770 1.0107 -6.15189 4e 1.0350 .9514 -9.8192 49 1.0120 .1872 -13.1271

• 0 .1350 7.800 -9.7679 51 .13600 .6966 5 .940 PEAKInG PARAMETER COMPARISON~

PARAMETER ]IEKS

• PREDICTED I IDInTILENCE FXY 1.5551 1.4800 5.0717 2 SR 1.4263 1.4100 1.1538 .

• z 1.1395 1.2200 2.6620 0 To 1.6446 1.6000 2.7893 %

CCiLK.i vi. VALUES

• 7ADL. 1- 2362-.

0 AXA1. - -49.55 50stm= AS.0 - -. 0523 PREDICTED3 AS. -. 0596 ACCEPTANCX CRITSRIA REPORT CASURmD 5= WAS WITUIN PLUS OR MINUS 10.000 0 Or TIM PREDCTED VALUE.

1A D FR WAS WITHIN PLUS OR MINUS 10.000 0 or THE PREDICTE vALE.

SURz I WAS WITHIN PLS OR MINUS 20.000 0 Or TIE PREDICT VALUE.

NEASURo To WA. WITUIW PLUS on MINUS 10.000 0 0? TEE PREDICTED VALUE.

ERARR CH AXIAL DISTRIBUTION AX WAS LESS THAM OR EOUAL TO 5.000 0.

R1M ERROR CH RADIAL DISTRIBUTIC01 WAS LESS TRAM OR EQUAL TO 5.000 0 ALL PREDICTZD ADIAL POWERS LESS IRAN 0.9 WERE WITWIN PLUS OR HINUS 15.000 s or MEASURED.

ALL PREDCTED RADIAL POWERS GREATER THAN OR EQUAL TO 0 .9 WERE WITHIN PLUS OR MIUS 10.000 0 or MEASURED.

• • ' ALL ACCEPTANCE CRITEPRA WERE MT **M

Attachment to 2CAN060502 Page 23 of 24 FIGURE 8 GETARP Output for the 100% Power Plateau 00G;20G0w ZZtc20! flUrr=r PA" PRISMR rPrtPr rP GMXGCG ESrTIL _T71 AAAMA RRaaPP9015 PPFPOPPPFP OGG 3 r AUAAAAAA M ' S rrPrF CG 00050 1r .5 .m7 AMAOA. 5ar05r50 15999911 002 GM 50 tLiG r; GG T5l5ECU155C -mTI 10 - mS

-"sA MA POA 515R 909 R PII 0rP .J psP rPr MICIGMUs 7mT AAAM MA PRR rtp GG*C4GGGGC 155515ES C 77 AMA AMA PRA 050P 00 MA7)

A r?9ogn To r r29A01 MIA 11OK CttCIA Sjwlo 7 r:VLE pea CtPARISO or AXI11 Am RADIAL roaL DOSTSIViflorS.

MMTR1071 - GETAAPtOP WI REVISION 1 MMs79D .5 7A X7aKME7DMOMH;.21415i.sOZ PracLC5201CASMC1t270ACM50: `1 aolp.d.q.100 RELAT7V RADIAL POWER DI557J020N COKPARI204J

k1*t1C71tb I .658 5 .550 t

561 ' ,SS1 g .'*16n WTJA.-01LEDIC751 I *EAS5rD  : . 414 .Stl .542: .537: .41S I DIFFEPZNCL 5 - - --- 0---X100.0 I T097MP

• I -2.17 1 -3.91 -2.24 I -3.50 I -4.66 j

, _ ____ _, ~~~~.__ ___............

P9I0T5tCD

.447 * .69 2.3025 M.1521.126 I.1552 1.15, .690 1 .4$55 J _.4S .455 1 07 a 2.145 .. 2.1l7 p 1.134 a 1.072 * . a -12 .121

-. 21a-1.7112.04 2 -. 40, -. 99 -1.42 -3.o0 -5.46*-1.21g

4.1 '_ 1 I::. _.: .,._ 'I .. l... ,__.__ I.................. _ __ _ _ .___+_

a .4}3) * .101 J 1.254J 1.116 J 1.466 a 1.152 a 1.550a 1.11 a 2.161 I 2.105* .455

• J .451 1.122 I.151 1.1 7 1.0 1.165, 1.064 1 1.14 a 2.:11 1.092 * .415

• 1 -.40 .42 -. 23, .51 -. 7 , -1.1? a -2.14 4 -. 3s -1.92 -1.45 -2.121

__ __. ____+

_ __ _ _ _ + _ _ _ _._ _ _ _. __ , _ ... ,...._..........

• .45 1 *1.10 2.2222

• 1J.155 1. 6' 1^.126

• 1:.05 I 1.137' I1.00 ' 1:.15* 1.220 1 1.107 J *44I *

• .402 a 1.12t

• 1.225 1.15 . .2.555 . 2.161* 1.672

• 1 .12 11.074 a2.15 *5.204 *1.095 .442 i 42.9051.10* .47 2.51, .756 2.02 - .*4a .05os -. 1a9 .29 -2.06 5 -2.C7 -1.030

• .69420 1 1aI 1.152 p 1.051 1.574a 5.1424.1.2 6 1.160 1.074 a 1.OSI

• 5.160 J 5.254 a .465 *

• .463 a 2.204 a I.2:5 , 1.042 a1.:16 a5.12 y1.5 41 1.153 , 1.154* 1.02** 1.264

• 5.1106 .660

• j -1.0 1. 1

• 2,.5 1 2.52 I 4.06 5 1.71 0 2.5I 2.01 I 2.15 -I.11 I .30 J -1.22 1 -4.15

.460 a 1.315

• 1.05 *'.I05 1.0174 : 1.071

• 2.125 1.239 a 2.11 , 1.071 a 1.0'4 a i.50o J 1.15C J 2.102 * .450 r

• .442 ; 1.104 I I.155

• 1.05] , 1.117 a .12 ,I 1.245 1 1.2S5 1.211 a 1.062 a 1.016 s 1.062 J 1.1S2 J 1.520 * .431 s a -2.53 -. 09 , 2.21

• 1.Z * .90 a 2.30 v 4.24 a 1.284 2.40 s .47a 1.40 * -1.64 i -. 50 i -3.36 a -5.93 s o .517

• 5.211

• 1.050

• 1.21 a 1.140

• 1.105 1.55.6

• 1.121 J 2.145

• 1.196 a 1.162 a 1.125 a 1.659 , 1.252 * .550 *

• .545* 1.145

• 1.00

• 1.151

• 1.192

• 1.255 0 1.2955 1.127 : 1.164

• 1.222

• 1.160 0 1.246

• 1.057 J 2.117 . .521 3-1.494 .979 .415 3.41 2.76 4.995 2.32 ' .14 , -. 34* 2.:: a-.20* .94a-2.02 -3.01 O -6..

,_ + __.___+__+__

.541 *1 1.152

• I.561 a 5.239 1.121

• 1.22 , 1.041, .1.21 a 1.229

• 5.121

• 1.045 a 1.212

• 1.22 * .541

• a .SS2

• 2:234

• 2.174

• 1.272 a 1.114 a 1.26 , 1.543 a 1.54 : 2.552 a 1.2213 *.124

• 1.023

• 1.25A I .094 * .526 a

• -1.42 a .50 a 1.6

• 5.19 6 4.91 2. I91.9S I .QL I -3.51 * -. 44 12.27 * -1.50 I -. 42: -3.04 I -4.11 J 4.......

4_*_

_._..._.__+____._______._

._. 4 -- -- -- -- - -- -- -

a .SS0 a 2.112 1 .569

• 5.111 0 1.152

• 1.15 0 1.161 *1421 a 1.165 1.192 a 1.260 *1.-22 - 1 1.0; 0 I 1.155 * .551 *

• .56

• 1.11 , 2.09 , 1.175

• 1.155 6 1.225

• 1.156

• 1.12 0 1 .159 1.219 a 1.241 6 1.144

• 1.054

• 1.117 1 .519 *

,-2. 5a .17C -. 01 a 3.4 I 3.078 4.90 t2.6: .46, -.. 14 2.C*O .10 .70 * -. 13 a -3.32 1 -2.9l1,

.41

• I 1.10 5 a 1.090 s 1.074 a 1.011 a 1.155 a 1.235 1 I.1S0 1.017 1 1.014* r 2.00 J 1.159 : 1.50S * .460 5

4 '.20 1.570 . 2.5 61'I . 15.091S

• 5.244 1.251 j 2.322 1.05 J 1.557 I 2.014 s 1.1252 1.062 * .419s5 a-2.06, -.56, 1.12, .51 2.!0, 1.65 24.10 1 .94 I2.011 .74i 2.14 1-l.t7 1 .99XI.49 I2.1

..-------------------------.-.- . -2!.I--_.4 -. $

a .6*9 a 1.254 a 2.150 a 2.511 , 1.514J 1.540 , 1.1l1, 1.142 a 1.574

• 1.011, 1.250* 1.155 .690 1 a .60a 5.222 M 2.225 a 1.052 1.109 . .... j.:11. : 2.172 S 1.1031 1.046 1.254* 1.112 a .cc2 a

• -. 11* 1.521 2.42* .I4f 23.30* L.31 ,4.90, .59 2.  : -. 24, I .47 1. -4.01 I

.447

• 1.107 6 1.232 a 2.150

• 1.050 J 1.137 g 1.045 2.116 8 1.000 O a 1.60 I 2.230 5 1.156 a .446

• .402

• 1.230 : 2.1205 1.20$ I 2.o51 5.367 I T ,.062

• 2.154 5 1.051 a 1.190

• 2.206 a 1.09) t .464

• 1.12 a 2.,06 .o05 2.10* -.25, 2.00 -. 24, 1.54: -1.02 .54*-2.Sc -. 51 -. 44,

• .455 a 2.10 Ia 1.151 J 1.156 I 1.592 a 1.052 I.CV9

• 1.1* J 1.164 J 1.101 I .49*

1 a .4641 1.107 a 1.17i 11.157 : 1.C45 6 1.153 a 1.06 a 1.146 1.142 12.559 3 .450 1

-. 59t -. 05 -. 42* -. 102a-23 * .I06 #-2.67 5-1.1I-1.1 2-1.63 1 -2.91 I

.445 a .I90  : 1.I1O J .115 a 1.526 a 1.152 a 1.152 * .659 a .467 a J .441 * .512

• 1.065 5 1.121 1.102 Z1.1205 1.59 * .645 5 .455 J -. 6 a -5.170 * -3.22 a -2.2 * -2.2 4 -2.01 -. 94 J -7.52 1 -2.56 J.40 J. ."57 * ."41 J .210 J .415, *

• .425 I .55 1 '.53 1 .19 a .4322

• -4.45 *-4.19 6 -5.06 * -5.61 a -'.4s J 925151TE AXIAL0POKER DlSSPIBt'SltN Ca405 PP REIC7TED - rSw. c51977927 I .7240 - - - .2645 -6.5021 2 .:770. . .. 171' -1.2177 2 1.140 -:.423 -14.95*0 4 1.0450 .521 -10.9*44 S 1.5s19 .9511 -4.441

• 1.0450 1.5257 -2.7115

• 1.04*0 1.5651 -.0524

• 1.0720 - .6 5.1241 9 1.0470 1.1554 3.2203 10Ia 1.oo I.1I13 2.9755 12 1.0132 - 1.102 4.1601 22 1.0200 1.0944 4.1560 12 1.0460 1.0605 2.1123

Attachment to 2CAN060502 Page 24 of 24 FIGURE 8 GETARP Output for the 100% Power Plateau (continued) 24 1.0420 1.0741 O.2l7S 15 1.035D 2.065 N.629D 16 I.033D I.0554 2.1664 17 1.0290 1.0471 1.7563 16 1.0250 1.040# 1.5451 19 I.0220 1.0367 1.442t 20 1.0200 1.0347 1.4420 21 1.010 1.0345 1.6167 22 1.01C0 1.0355 1.9235 23 1.0150 1.0375 2.2141 24 I.0150 - 1.0397 2.4375 25 1.0160 1.0419 2.547D 26 1.0190 1.0435 2.4049 27 1.0220 1.0444 2.1086 28 1.0230 1.0443 2.0862 29 1.0220 1.0434 2.0986 30 . 1.0210 1.041i 2.0409 31 1.0190 1.0397 2.0360 32 1.0160 1.0375 2.1139 33 1.0140 1.0353 2.1039 34 1.0120 1 0336 2.132D 35 1.0100 -1.0324 2.2143 36 1.0080 1.0317 2.3525 37 1.0050 1.0314 2.6315 39 1.0020 1.0312 2.9122 39 1.0000 2.0303 3.0304 40 .9970 1.0280 3.1083 41 .9940 1.0232 2.9393 42 .9900 - 1.0148 2.5062 43 .9e50 -; l.D015 1.6753 44 .9770 .9020 .5106 45 .96S0 .9550 -1.1371 46 .9510 .9195 -3.3114 47 .9330 .8744 -6.2849 48 .9100 .8l91 -9.9912 49 .8700 - .7533 --

13.4179 50 .7640 -. 6769 -11.3952 51 .4470 .5905 -E.7288 PEAXING PARAHE7ER COMPARISON PARAt0TER FEAS. PREDICTED I DIFMRENCE mXY 1.5244 1.4700 3.1014 k TR 1.4070 1.3900 1.2022 .

Il 1.1053 1.0700 3.2983 i ro 1.7067 1.S5D0 10.1127 k CALCUtATED RMS VALUES RADIAL - 2.3774 AXIAL - 4.1633 KEASRED A51 = .0263 PREDICTED AS - .0266 ACCEPTANCE CRITERIA REPORT

1. lASURED FXY WAs NITHIN PLUS OR MlN'US 10.00Q 1 OF THE PREDICTED VALtE.

KEASURED FR WAS WITHIN PLUS OR HIIWJS 10.000 i OF THE PREDICTED VALVE.

MEASURED rz hAS WItHIN PLUS OR MIKUS 10.000 t OF TSE PREDICTED VALUE.

4WARNINGNMEASURED FO WAS NOTWNIflI PLUS OR MINUS 10.000

• OF THE PRlDICTED VALUE.

RMS ERROR ON AXIAL DISTRIBVT10tI WAS LESS THAN OR EQUAL tO 5.000 ;.

RNS ERROR ON RADIAL DISTRIBUTION WAS LESS TNAN OR EQUAL TO 5.000 t.

ALL PREDICTED RADIAL POWERS LESS TION 0.9 WERE WITHIN PLUS OR MINUS 15.000 t OF MEASURED.

ALL PREDICTED RADIAL POWERS GREATER THaN OR EQUAL TO D.9 WER" WITHIN PLUS OR MIKUS 10.000 1+/- OF MEASURED.

• WAR1INDSALL ACCEPTANCE CRITERIA WERE FO0TMET