Text

Suppl 1 to Qualification of Reactor Physics Methods for Application to PWRs of Middle South Utils Sys,Waterford Steam Electric Station Unit 3,Method Validation
	ML20210R339
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Site:	Waterford
Issue date:	09/15/1986
From:	Thompson S; MIDDLE SOUTH SERVICES, INC.
To:	;
Shared Package
ML20210R318	List: ML20210R312; ML20210R339; W3P86-3328, Boric Acid Concentration Reduction Effort,Technical Bases & Operational Analysis,Waterford Nuclear Power Plant Unit 3;
References
	MSS-NA1-P-S01, MSS-NA1-P-S1, NUDOCS 8610070274
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ATTAC10ENT 4 QUALIFICATION OF REACTOR PHYSICS METHODS FOR APPLICATION TO PRESSURIZED WATER REACTORS OF THE MIDDLE SOUTH UTILITIES SYSTEM MSS-NAl-P SUPPLEMENT #1 l

Middle South Services, Inc.

225 Baronne Street New Orleans, LA 70161 September 1, 1986

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QUALIFICATION OF REACTOR PHYSICS METHODS FOR APPLICATION TO PRESSURIZED WATER REACTORS OF THE MIDDLE SOUTH UTILITIES SYSTEM WATERFORD STEAM ELECTRIC STATION UNIT 3 METHODS VALIDATION R. B. LANG R. A. JENSEN R. E. GRIFFITH S. G. SHUE Reviewed by 9!/2//4 -

Lead / Nuclear Engineer Date Reactor Physics Anal Section Approved by A 9!/ [0 Manager % / Dgte Reactor Physics Analysis Section l

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MSS-NAl-P Sucolement 1 Pace 3 ABSTRACT The purpose of this supplement is to demonstrate that the reliability factors presented in MSS-NAl-P [2] are appropriate for application to physics parameters determined by Middle South Services, Inc. in support of the Waterford Steam Electric Station Unit 3 (WSES-3). This supplement extends the model validation presented in atSS-NAl-P for Arkansas Nuclear One Units 1 and 2 to WSES-3. In the 1982 NRC safety evaluation report of MSS-NAl-P [1], the physics methods and reliability factors were not approved for WSES-3 use because comparisons of predictions to WSES-3 measurements were not yet available. This supplement provides comparisons between measurements and predictions for WSES-3 and establishes the reliability factors appropriate for WSES-3 application.

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Page 4 TABLE OF CONTENTS

1. INTRODUCTION . . . . . . . . . . . . . . . . . . . . . . . . 8

2. OVERVIEW OF THE CALCULATIONAL MODEL . . . . . . . . . . . . 9

3. MODEL VERIFICATION & RELIABILITY . '. . . . . . . . . . . . . 10 3.1. Rod Worth and Soluble Boron Coefficient . . . . . . . . . 13 3.2. Temperature Coefficient . . . . . . . . . . . . . . . . . 17 3.3. Doppler Coefficient & Doppler Defect . . . . . . . . . . 20 3.4. Isotopics . . . . . . . . . . . . . . . . . . . . . . . . 21 3.5. Delayed Neutron Parameters . . . . . . . . . . . . . . . 23 3.6. Power Distribution Uncertainties . . . . . . . . . . . . 23 3.6.1. Nodal Power Distributions . . . . . . . . . . .. . . . 23 3.6.2. Local Power Distributions . . . . . . . . . . . . . . 37 3.7. Power Distribution Reliability Factors . . . . . . . . . 37 3.7.1. F Reliability Factors . . . . . . . . . . . . . 37 3.7.2. F g Reliability Factors . . . . . . . . . . . . . . . 38

4. MODEL APPLICATIONS TO REACTOR OPERATIONS . . . . . . . . . . 39 i

5. MODEL' APPLICATIONS TO SAFETY EVALUATIONS . . . . . . . . . . 40

6. REFERENCES . . . . . . . . . . . . . . . . . . . . . . . . . 41

7. APPENDIX A TYPICAL WSES-3 POWER DISTRIBUTION COMPARISONS . . 42

Page 5 LIST OF TABLES TABLE 3.1 PHYSICS RELIABILITY FACTORS FOR WSES-3 . . . . . . . . . . 12 TABLE 3.2 MEASURED AND CALCULATED ROD WORTHS . . . . . . . . . . . . lb TABLE 3.3 MEAS. AND CALC. ISOTHERMAL TEMPERATURE COEFFICIENTS . . . . 19 TABLE 3.4 SAXTON ISOTOPICS: EPRI-CELL / CPM COMPARISONS TO EXPERIMENT . 22 TABLE 3.5 REACTOR STATE POINTS WSES-3 CYCLE 1 . . . . . . . . . . . . 28 TABLE 3.6 INFERRED S.D. OF MEASUREMENT ERRORS FOR WSES-3 CYCLE 1 . . 29 TABLE 3.7 RMS OF MODELING ERROR FOR WSES-3 CYCLE 1 . . . . . . . . . 30 TABLE 3.8 POOLING METHODOLOGY . . . . . . . . . . . . . . . . . . . . 31 TABLE 3.9 POOLED RMS OF MODEL ERROR AND RELIABILITY FACTORS . . . . . 33 1

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Page 6 LIST OF FIGURES FIGURE 3.1- MEAS. TO CALC. ROD WORTH COMPARISONS . . . . . . . . . . . 16 FIGURE 3.2 WSES-3 IN-CORE Rh LOCATIONS . . . . . . . . . . . . . . . 34 FTGURE 3.3 AXIAL LOCATIONS OF IN-CORE Rh DETECTORS FOR WSES-3 . . . . 35 _

FIGURE 3.4 CONTROL ELEMENT ASSEMBLIES (CEA) FOR WSES-3 . . . . . . . 36 FIGURE A.1 MEAS. AND CALC. INTEGRAL REACTION RATES AT 22 EFPD . . . . 43 FIGURE A.2 MEAS. AND CALC. REACTION RATES STRING 20, 22 EFPD . . . . 44 FIGURE A.3 MEAS. AND CALC. REACTION RATES STRING 32, 22 EFPD . . . . 45 FIGURE A.4 MEAS. AND CALC. REACTION RATES STRING 39, 22 EFPD . . . . 46 FIGURE A.5 MEAS. AND CALC. INTEGRAL REACTION RATES AT 146 EFPD . . . 47 FIGURE A.6 MEAS. AND CALC. REACTION RATES STRING 20, 146 EFPD . . . . 48 FIGURE A.7 MEAS. AND CALC. REACTION RATES STRING 32, 146 EFPD . . . . 49 FIGURE A.8 MEAS. AND CALC. REACTION RATES STRING 39, 146 EFPD . . . . 50 FIGURE A.9 MEAS. AND CALC. INTEGRAL REACTION RATES AT 261 EFPD . . . 51 FIGURE A.10 MEAS. AND CALC. REACTION RATES STRING 20, 261 EFPD . . . 52 FIGURE A.11 MEAS. AND CALC. REACTION RATES STRING 32, 261 EFPD . . . 53 FIGURE A.12 MEAS. AND CALC. REACTION RATES STRING 39, 261 EFPD . . . 54

MSS-NAl-P Sucolement 1 Pace 7 4

1. INTRODUCTION MSS documented the reliability factors associated with MSS physics methods for MSU Pressurized Water Reactors Arkansas Nuclear One Unit 1 (ANO-1) and Arkansas Nuclear One Unit 2 (ANO-

2) in MSS-NAl-P [2]. No comparisons between predictions and measurements for WSES-3 were available in 1982 when Reference 2 was issued and approved by the NRC. The purpose- of this supplement is to demonstrate that the reliability factors presented in MSS-NAl-P are appropriate for application to physics parameters determined by Middle South services, Inc. in support of the Waterford Steam Electric Station Unit 3 (WSES-3).

This supplement describes the methodology used at Middle South Services (MSS) to determine calculational uncertainties, presents the resultant reliability factors associated with the MSS ARMP reactor physics model derived from a Waterford Steam l Electric Station Unit 3 (WSES-3) model validation effort (Sections 2 and 3), and indicates the methodology for applying the MSS ARMP model to WSES-3 reactor operations (Section 4) and safety evaluations (Section 5) . The aspects of model validation are stressed more than code descriptions which are available in j the EPRI ARMP references cited in Section 6. T*.t e organization of this supplement is the same as the base report.

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e ----,m - - en MSS-NAl-P Sucolement 1 Pace 8 The uncertainties are evaluated by direct comparison to experimental data. Whenever possible, directly observable parameters such as boron concentrations and incore detector reaction rates are utilized. This evaluation considered the available Cycle 1 WSES-3 data. Fifteen incore detector reaction rate maps were chosen to cover the available Cycle 1 core average exposure range at approximately equal exposure steps.

Maps at reduced core power and with control rods inserted were also included in the data base.

After the measured data to be used in the validation process had been defined, the model calculations were performed and comparisons were made to all the above qualified measured data.

l A statistical approach was used to derive the uncertainties, f

These uncertainties are consistent with the model application

procedures and methodology. The resulting reliability factors were found to be conservatively bounded by the reliability factors presented in MSS-NAl-P with the exception of the reliability factor to be used with small control rod worths (e.g., single control rod bank or single control rod) for which a more conservative value of 0.10 was chosen. Therefore the reliability factors presented in MSS-NAl-P and in Table 3.1 are appropriate for application to WSES-3.

MSS-NAl-P Sucolement 1 Pace 9

2. OVERVIEW OF THE CALCULATIONAL MODEL The model used to analyze the core was constructed using the Advanced Recycle Methodology Program [3] (ARMP) system developed under Electric Power Research Institute (EPRI) sponsorship. The description of the code system is identical to that described in Section 2 of MSS-NAl-P [2] and is not repeated here.

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MSS-NAl-P SuoDiement 1 Pace 10

3. MODEL VERIFICATION & RELIABILITY The MSS ARMP model for WSES-3 has been verified against WSES-3 measurements made during cycle 1, to quantify the reliability factors to be used in safety related calculations. The resulting reliability factors and biases are summarized in Table 3.1. The remainder of this section is a detailed account of the derivation of these factors.

The term reliability factor (RF) is used to describe the allowances to be used in safety related calculations to assure conservatism. The uncertainty factor (la) is used to describe the actual model accuracy at the one sigma level.

The reliability factor is always larger than the uncertainty factor. The term bias is used to describe the average difference between an observed or measured parameter and the calculated value.

Except for temperature coefficient, all reliability factors and biases in Table 3.1 are dimensionless constants which are applied to the results of ARMP calculations as shown below. The reliability factor and bias for temperature coefficient are additive corrections to ARMP calculations.

In general the conservative estimate of a parameter X is related to the ARMP calculational parameter through the

I' MSS-NAl-P SuoDiement 1 Pace 11 following equation:

X =

(1- as i F)

X

SAFETY X ARMP Xgp = ARMP calculations of parameter X X = Conservative estimate of parameter X for SAFETY use in performing safety evaluations.

RF = Reliability factor appropriate to X

parameter X Bias = Bias appropriate to parameter X X

Refer to Section 5.0 of MSS-NAl-P for specific details of procedures for application of reliability factors and model biases, d

MSS-NAl-P Sucolement 1 Pace 12 TABLE 3.1 PHYSICS RELIABILITY FACTORS FOR WSES-3 PHYSICS -

PARAMETER RELIABILITY FACTOR BIAS Fg 0.10 0 F 0.057 0 AH Rod Worth (pattern) 0.05 0 Rod Worth (bank or 0.10 0 single rod)

Temperature 4.0 PCM/*F 0 Coefficient Doppler 0.10 0 Coefficient Doppler 0.20 0 Defect Boron Worth 0.05 0 Delayed 0.03 0 Neutron Parameters

MSS-NAl-P SuoDiement 1 Pace 13 3.1. Rod Worth and Soluble Boron Coefficient During the rod worth dilution measurements, critical coluble boron concentrations are measured at various stages of rod insertion. The accuracy of the soluble boron concentration measurements are limited only by the titration accuracy which is estimated to be better than 2%. The approach taken here then is to validate the MSS ARMP model for WSES-3 to the directly observable parameter, soluble boron.

The data used in the validation represent the actual measured critical state-points. All WSES-3 measured state-points were included. Measured data is presented for two other C-E designed reactors with 16 X 16 fuel pin assemblies. The results are shown in Table 3.2.

The incremental rod worths have been calculated as the difference from a nearly unrodded reference state-point and have been computed in terms of PPM of boron change from the reference. Figure 3.1 is a plot of measured rod worths versus predicted rod worths. The error bands on the measured rod worths correspond to the differences anticipated due only to an uncertainty in the boron titration measurements of the boron end points. The boron concentration titration uncertainty is approximately 1% of the boren eoncentration.

MSS-NAl-P Supolement 1 Pace 14 Using the relationship between observed uncertainty, titration measurement ancertainty, calculational rod worth uncertainty and calculational boron worth uncertainty presented in section 3.1 of MSS-NAl-P [2), the observed uncertainty is of the same magnitude as the measurement (titration) uncertainty. This is shown graphically in Figure 3.1. It is inferred therefore that the uncertainties due to calculational rod worth (op) and the calculational boron worth coefficient (oB) are quite small. For cen$ervatism, however, the rod worth reliability factor (RFrods) and thA boron worth coefficient reliability factor (RFB) "#8 both defined as 0.05.

The rod worth comparisons provided in Table 3.2 are for pattern worths (several rod banks together). For a single control rod bank or an individual control rod, a more conservative value of 0.10 is used for the reliability factor.

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MSS-NAl-P SuoDiement 1 Pace 15 TABLE 3.2 MEASURED AND CALCULATED ROD WORTHS POSITION MEASURED INCREMENTAL ROD (INCHES BORON ROD WORTH (PPM)DIFF.

REACTOR BANK WITHDRAWN) (PPM) Meas. Calc. (PPM)

ANO2 6 119 1006 8 3 -5 ANO2 6-3 0 833 181 179 -2 2 98 ROD 6-1 150 ANO2 6-3 0 833 181 182 +1 2 95 ROD 4-11 150 ANO2 6-3 0 809 205 202 -3 2 98 ANO2 6-1 0 658 356 352 -4 SDB 123 ANO2 6-1 0 632 382 376 -6 SDB 83 SONGS 2 6-3 0 629 204 200 -4 SONGS 2 6-1 0 499 334 333 -l WSES3 6-3 0 620 209 200 -9 WSES3 6-1 0 507 322 333 +11 1

ANO-2 data reproduced frort MSS-NAl-P.

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MSS-NAl-P Sunnlement 1 Pace 16 FIGURE 3.1 MEAS. TO CALC. ROD WORTH COMPARISONS WITH 1% BORON TITRATION ERROR BARS o

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MSS-NAl-P Supolement 1 Page 17 3.2. Temperature Coefficient This section investigates the MSS model bias and uncertainty for calculating temperature coefficients.

Measurements of the isothermal temperature coefficient can be adequately made with a reactivity computer if the rate of temperature change is slow and there is no rod motion. For measurements made at power care must be taken in assuring equilibrium xenon conditions prior to conducting the test. The impact of xenon changes can be limited if the total elapsed time for the test is minimized.

Comparisons of the maasured and calculated ITC's are presented in Table 3.3. Included in this comparison are six ANO-1 measurements, five ANO-2 measurements and seven WSES-3 measurements. Data from all MSU PWRs were combined to determine a PWR temperature coefficient reliability factor.

In the original development of a reliability factor for temperature coefficient calculations made for ANO-1 and ANO-2 (2], a rigorous statistical approach was not taken. Instead, a conservative value of 4 PCM/*F was assigned as the reliability factor and a value of 0 was assigned as the bias. The conservatism of a 4 PCM/*F reliability factor on ITC was

1 MSS-NAl-P Supolement 1 Pace 18 justified on the basis that all of the AITC's were less than 4 PCM/*F. To ensure the assigned 4 PCM/*F reliability factor is conservative for WSES-3 as well as ANO-1 and ANO-2, a statistical reliability factor was calculated based on the eighteen measurements in Table 3.3. The resultant 3.4 PCM/*F reliability factor is conservatively bounded by the previously assigned 4 PCM/*F reliability factor. The assignment of a zero bias is also supported by the WSES-3 data since it did not exhibit a bias. Therefore the PWR temperature coefficient reliability factor of 4.0 PCM/*F can be applied conservatively to WSEE-3.

/

MSS-NAl-P Sucolement 1 Pace 19 TABLE.3.3 MEAS. AND CALC. ISOTHERMAL TEMPERATURE COEFFICIENTS Rod Bank Boron ITC(PCM/*F) AITC(PCM/'F)

Reactor Cycle Position opm Meas. Calc. (Calc. - Meas.)

ANO, Unit 1 1 7 = 73% 1566 +4.3 +1.7 -2.6 6 = 74% 1442 +2.8 +1.8 -1.0 5 = 21% 1270 -3.6 -4.8 -1.2 4 = 39% 1183 -6.2 -6.4 -0.2 2 5= 4% 1050 -7.6 -7.2 +0.4 3 7 = 75% 1350 +1.8 +0.7 -1.1 RNO, Unit 2 1 6 = 80% 1004 +0.3 -0.5 -0.8 2 = 65% 808 -4.8 -4.6 +0.2 B = 80% 657 -10.7 -9.7 +1.0 ARO 1230 +0.4 -0.7 -1.1 3 = 40% 1040 -3.9 -3.9 0.0 WSES, Unit 3 1 ARO 829 -3.9 -3.0 +0.9 6-3 = 0% 620 -10.3 -9.3 +1.0 6-1 = 0% 507 -15.3 -12.3 +3.0 ARO 296 -12.0 -14.2 -2.2 ARO 550 -7.6 -8.5 -0.9 ARO 487 -10.3 -10.9 -0.6 ARO 507 -9.3 -10.5 -1.2 n = 18 , K = 2.453 95/95 31.8 = [ (AITCg) o= (31.8/17)* = 1.37 RF = K *# " * ** " * !

95/95 l

l MSS-NAl-P Supolement 1 Pace 20 3.3. Dopoler Coefficient & Donoler Defect Direct measuremont of the Doppler coefficient has not been performed at WSES-3. Therefore, as in Section 3.3 of MSS-NAl-P, conservative values for model reliability with respect to Doppler reactivity effects have been defined.

The ARMP model Doppler Reliab.llity Factors for application to WSES-3 are defined as follows:

Doppler Coefficient, o = .10 DC Doppler Defect , ODD =. O Because it is not possible to directly measure the Doppler coefficient at WSES-3, the reliability factors were shown to be conservative by calculating the Doppler coefficients and comparing them to EPRI experiments. The results [4] were uncertainties of 2.90% and 7.23%. In view of this, the 10%

reliability factor placed on the Doppler coefficient for WSES-3 was judged adequate and conservative.

MSS-NAl-P Sunclement 1 Pace 21 3.4. Isotonics The EPRI-CELL computer code is used for the calculation of isotopic data for WSES-3 as it was for ANO-1 and ANO-2 in MSS-NAl-P. Therefore the benchmarking of EPRI-CELL / CPM against experiments presented in Section 3.4 of MSS-NAl-P is applicable to WSES-3. Comparisons of isotopics presented in MSS-NAl-P and reproduced in Table 3.4 are also applicable to WSES-3.

MSS-NAl-P Sucolement 1 Pace 22 TABLE 3.4 SAXTON ISOTOPICS: EPRI-CELL / CPM COMPARISONS TO EXPERIMENT ~

l l l Experimental l CPM-exp l l Nuclide l Experiment l uncertainty l ------- x 100 l l l l % l exp l l '

l l Atom % l l l l l l l l l U-234 l 0.00465 l 28.7 l 15.9 l l l l l l l U-235 l 0.57400 l 0.9 l -0.3 l l l l l l l U-236 l 0.03550 l 5.6 l 2.8 l l l l l l l U-238 l 99.38600 l 0.0 l 0.0 l l l l l l l Pu-238 l 0.10900 l 2.2 l -11.4 l l l l l l l Pu-239 l 73.77000 l 0.0 l -0.3 l l l l l l l Pu-240 l 19.25000 l 0.2 l 1.6 l l l l l l l Pu-241 l 6.29000 l 0.3 l 0.4 l l l l l 1 Pu-242 l O.57900 1 0.9 I -16.0 1 1

l Atom Ratios l l l l l l l l

_4 l Np-237/U-238 l 1.14x10 l 15.0 l -26.4 l l l l l l l Pu-239/U-238 l 0.043830 l 0.7 l 0.2 l l l I I I

_3 l Pu-238/Pu-239 l 1.75x10 l 0.4 l -9.8 l l l l l l l Am-241/Pu-239 l 0.012300 l 15.0 l -10.6 l l l I I I

_4 l Cm-242/Pu-239 l 1.05x10 l 10.0 l 0.0 l l l I I I

_4 l Cm-244/Pu-239 l 1.09x10 l 20.0 l 0.0 l l l l I I s

MSS-NAl-P Sunclement 1 Pace 23 3.5. Delaved Neutron Parameters The two important values of delayed neutron parameters are the effective delayed neutron fraction (p,gg) and the effective neutron lifetime 1 .

The components of uncertainty in p,gg and 1 are identified in Section 3.5 of MSS-NAl-P. The calculation of rellebility factors for p,gg and 1* in MSS-NAl-P is applicable to WSES-3 and results in the following reliability factors and biases.

RF = 0.03 BIAS = 0 g

A = 0.03 BIAS = 0 3.6. Power Distribution Uncertainties 3.6.1. Nodal Power Distributions The WSES-3 model reliability factors for calculating power distributions are based on comparisons of measured and predicted in-core flux detector signals for normal operating

MSS-NAl-P Sunclement 1 Pace 24 core conditions.

The WSES-3 care is instrumented with 280 self-powered Rh detectors. These detectors are 40 centimeters long and are distributed at five axial core levels in the central water hole of 56 different fuel assemblies. The actual radial and axial locations of the Rh detectors are shown in Figures 3.2 and 3.3 respectively.

The signals from these detectors are corrected by the on-site process computer to account for such things as datector sensitivity, depletion, background and leakage. It is these corrected signals, or reaction rates, which have been compared to simulated reaction rates calculated with MSS ARMP model in order to derive the model reliability factors. The simulated detector signals are calculated from the nodal code as described in Section 3.6.1 of MSS-NAl-P.

Fifteen core state-points were used for comparing measured and simulated incore reaction rates. The specific core conditions are given in Table 3.5. In all comparisons, both the predicted and measured reaction rates have been normalized to a core average value of unity for each map.

MSS-NAl-P Sucolement 1 Pace 25 Typical. examples of the comparisons of measured and predicted reaction rates are provided in Appendix A, Figures A.1 - A .12 .

The data is presented in sets of four figures, one set for each flux map. Flux maps were chosen as being representative of beginning, middle, and near end of cycle power shapes. The first figure in each set presents differences between the measured and calculated integral reaction rates at all working detector locations.

The second through fourth figures in each set present axial comparisons in three specific instrumented core locations. The measurements are shown at the five axial levels defined in Figure 3.3. The predicted reaction rates are represented as continuous functions. The three core locations were chosen as being representative of the core central, middle and outer regions and different fuel types.

Individual measured dctector reaction rates from all detector locations were compared to model predictions and standard deviation of the observed relative differences were computed at each of the five detector levels.

The distribution of observed differences between measured and calculated instrument signals were tested for normality using the Chi-Square Test. The results demonstrated that the i

l MSS-NAl-P SuDolement 1 Pace 26 distributions agreed well with theoretical normal distributions on a level by level basis. However, if all axial levels were lumped together, the observed distributions differed significontly from normal distributions. Therefore, all subsequent statistical analysis has been performed on a level by level basis.

Statistics are obtained for each of the five detector levels, for each state-point as described in Section 3.6.1 of MSS-NAl-P.

The standard deviations of the measurement errors are presented in Table 3.6. The root mean squares (RMS) of the modeling error are presented in Table 3.7.

Individual map statistics were pooled to obtain a conservative estimate of the model uncertainties. The first step towards pooling was to test the statistics in Table 3.7 to see if they represented populations of equivalent variances. A conservative approach to this objective was to apply the Bartlett Test to the model error statistics as shown in Table 3.8.

Table 3.9 presents the pooled modeling uncertainties at each level, using the RMSmodel( ) data presented in Table 3.7. The model uncert:'.inty for the channel integral calculation, RMS (channel) model, was determined by pooling values presented in Table 3.7. This results in a pooled RMS(channel)model

l MSS-NAl-P Supplopent 1 Pace 27 uncertainty of 1.6 as shown in Table 3.9.

MSS-NAl-P Supplement 1 Pace 28 TABLE 3.5 REACTOR STATE POINTS WSES-3 CYCLE 1 BURNUP MAP # POWER % DATE EFPD ROD POSITIONS 1 51. 04/21 3.31 ARO 2 50. 04/24 5.01 BK6 IN 3 100. 07/03 22.44 ARO 4 99. 10/01 35.17 ARO 5 100. 11/11 64.17 ARO 6 98. 11/25 78.04 ARO 7 100. 12/30 99.24 ARO 8 100. 01/13 112.10 ARO 9 100. 02/17 145.51 ARO 10 100. 04/07 171.43 ARO 11 100. 04/21 185.69 ARO 12 100. 05/07 199.40 ARO 13 100. 05/22 212.00 ARO 14 100. 06/09 229.30 ARO 15 100. 07/22 261.30 ARO

MSS-NAl-P Sucolement 1 Pace 29 TABLE 3.6 INFERRED S.D. OF MEASUREMENT ERRORS FOR WSES-3 CYCLE 1 (TOP---------LEVEL--------BOTTOM)

MAP # 5 4 3 2 1 INTEGRAL 1 1.5 1.8 2.0 1.8 1.9 1.3 2 1.5 1.8 2.0 1.8 1.8 1.3 3 1.9 1.9 2.0 2.2 2.8 1.4 4 2.7 1.7 1.9 1.8 1.9 1.4 5 1.4 1.6 1.8 1.7 1.8 1.2 6 1.4 1.6 1.8 1.7 1.7 1.1 7 1.3 1.5 1.7 1.6 1.7 1.1 8 1.3 1.5 1.7 1.6 1.7 1.0 9 1.3 1.5 1.5 1.5 1.6 0.9 10 1.2 1.5 1.5 1.5 1.5 0.9 11 1.2 1.5 1.5 1.5 1.5 0.8 12 1.3 1.5 1.4 1.5 1.4 0.9 13 1.3 1.5 1.5 1.5 1.7 0.9 14 1.2 1.5 1.5 1.6 1.4 0.9 15 1.2 1.5 1.5 1.8 1.4 0.9 4

MSS-NAl-P SuDolement 1 Pace 30 TABLE 3.7 RMS OF MODELING ERROR FOR WSES-3 CYCLE 1 l (TOP---------LEVEL--------BOTTOM)

! MAP # 5 4 3 2 1 INTEGRAL i

1 2.6 1.7 2.8 1.5 2.6 1.7 l

2 2.6 1.5 3.0 1.3 3.2 1.3 3 2.2 1.4 2.5 1.6 3.5 1.6 1

4 2.0 1.0 2.6 1.0 3.6 1.0 5 2.2 1.1 2.5 1.2 3.9 1.1 6 2.5 1.3 2.6 1.3 4.7 1.1 7 2.5 1.0 2.1 1.0 3.4 0.9 8 2.9 1.2 1.8 1.1 2.6 0.9 9 1.2 2.0 1.4 1.1 1.2 0.8 10 4.3 2.0 1.3 1.6 1.2 0.9 11 2.7 2.5 1.2 1.6 1.5 1.1 12 1.7 3.1 1.3 1.6 2.0 1.1 13 1.5 3.1 1.4 1.8 2.1 1.3 14 1.5 3.5 1.7 2.0 2.9 1.5 ,

15 2.5 3.4 2.7 2.4 3.6 1.7 l

l l

h

MSS-NAl-P Sucolement 1 Pace 31 TABLE 3.8 POOLING METHODOLOGY (a) Using Bartlett's test, test for poolability by level for i

all maps. If data passes BP.rtlett's test; determine a pooled and K corresponds to the sample size of N, 95/95* 95/95 The reliability factor will be no less than N=[all w (N g) .

i K * #

pooled. not, go to @).

95/95 1

(b) Using Bartlett's test, test for poolability by level for individual cycles of data. If not poolable, go to (c). If all cycles are individually poolable, determine p#] d and K corresponds to the same sample size of N, 95/95* 95/95 N=[,71 ,p,(Ng ). The reliability factor will be no less than the maximum of K *# d*

95/95 p i

(c) If data is poolable except for maps which have a very small standard deviation, eliminate these maps for that level and retest for poolability. If all maps are poolable, then determine a pooled and K corresponds to a sample 95/95* 95/95 size of N, N is defined as the total number of comparisons in the reduced set. If only poolable by cycle (for all cycles), then determine the cycle specific apooled and K 95/95*

The reliability factor will be no less than the maximum of K *# pooled. not, go to W .

95/95

MSS-NAl-P Sucolement 1 Pace 32 (d) Determine K 95/95 * #

maximum fr each cycle. a maxima is the maximum of the level standard deviation in the cycle or the o standard deviation for that cycle (if poolable).

pooled K corresponds to the number of comparisons used in the 95/95 determination of a,,x1, ,. The reliability factor will be no less than the maximum of K *#

95/95 maximum

MSS-NAl-P Succlement 1 Pace 33 TABLE.3.9 POOLED RMS OF MODEL ERROR AND RELIABILITY FACTORS FOR WSES-3 1

AXIAL LEVEL NUMBER OF COMPARISONS RMS modek U) c[ ] RF 5 55 4.3 2.042 .096 4 272 3.1 1.809 .066 3 446 2.6 1.774 .057 2 168 2.1 1.856 .053 1 379 3.7 1.783 .074 INTEGRAL 209 1.6 1.835 .046 1

From Sections 3.7.1 and 3.7.2.

I l

MSS-NAl-P SuDDlement 1 Pace 34 FIGURE 3.2 WSES-3 IN-CORE Rh LOCATIONS A B C D E F GHJKLMNPR S T V W X Y l.................................. . . . . . . . .

2.................................. 1 2 3 4 5 . . . .

d 3............................. . . .

4..................... 6 7 8 9 10 11 12 5............. .

6............. 13 14 15 16 17 18 19 7.....

8..... 20 21 9..... 22 23 24 25 26 27 28 10 .....

11.....

12.....

13..... 29 30 31 32 33 34 35 14..... 36 37 15..... -

16 . . . . . . . . . . . . . 38 39 40 41 42 43 44 17 . . . . . . . . . . . . .

18..................... 45 46 47 48 49 50 51 19.............................

20..................................... 52 53 54 55 56 21......................................................... * -DETECTOR NUMBER

MSS-NAl-P Supolement 1 FIGURE 3.3 AXIAL LOCATIONS OF IN-CORE Rh DETECTORS FOR WSES-3 h

Rh Detector Level 5 Level 4

-3 0. 0" Active Fuel 4 Level 3 150" p Rh Detector Level 2 I "

-14.3" Level 1 A

i

MSS-NAl-P Supplem^nt 1 Paga 36 FIGURE 3.4 CONTROL ELEMENT ASSEMBLIES (CEA) FOR WSES-3 A B C D E F GHJKLMNPR S T V W X Y

. . . . . . t . . . . . .

1.................................. . . SDA . . . . . .

. l . . . .

2.................................. 2 2 . . . .

3............................. SDB 3 4 3 SDB .

4..................... 1 SDA SDB SDB SDA 1 .

5............. SDB 5 PLR 6 PLR 5 SDB 6............. SDA SDA SDB SDB SDA SDA 7..... 3 PLR 4 1 4 PLR 3 8.....

9..... 2 SDB SDB SDA SDB SDB 2 10.....

11..... -S Dk 4 6 1 2* 1 6 4

-S Dk

( 12..... 2 13..... 2 SDB SDB SDA SDB SDB 14.... 3 15..... 3 PLR 4 1 4 PLR 16............ SDA SDA SDB SDB SDA -

SDA 17 . . . . . . . . . . . . SDB 5 PLR 6 PLR 5 SDB 18.................... 1 SDA SDB SDB SDA 1 19............................ SDB 3 4 3 SDB 20.................................... 2 2 21........................................................ SbA l SDA-Shutdown A CCenter CEA is assignable SDB-Shutdown B to any regulating group PLR-Part-Length

MSS-NAl-P SuDDiement 1 Pace 37 3.6.2. Local Power Distributions ANO-2 and WSES-3 both use fuel assemblies of a common 16 X 16 fuel pin design. The ANO-2 uncertainty and bias presented in MSS-NAl-P on peak to average fuel pin peaking within an assembly are therefore applicable to WSES-3. Based on MSS-NAl-P, the following statistics are appropriate to the calculation of pin factors using the MSS ARMP model on 16 X 16 fuel assemblies of the design found in WSES-3 and ANO-2.

pin factor uncertainty, S p = .020 pin factor bias, AFp = .001 3.7. Power Distribution Reliability Factors 3.7.1. g Reliability Factors i

Local peaking factors such as F g or linear heat rate (LHR) are computed with the MSS ARMP model using the same procedure as described in Section 3.7.1 of MSS-NAl-P.

Table 3.9 contains the pooled model RMS, (RMSmodel), the factor for one-sided tolerance limits at the 95/95 probability /

confidence level, (K ) ,

c and the reliability factors, (RF),

l l

I MSS-NAl-P Sucolement 1 Pace 38 calculated as in Section 3.7.1 of MSS-NAl-P.

A bounding value of 9.6% was found for RF pg. However for consistency the more conservative value of 10% determined in Section 3.7.1 of MSS-NAl-P will be used.

3.7.2.Eg Reliability Factors The hot channel peaking factor; Fg is computed with the MSS ARMP model for WSES-3 using the procedure described in Section 3.7.2 of MSS-NAl-P.

The critical factor K c

was determined from the number of comparisons pooled. Therefore, the value of K c appropriate to RF 7g is defined as 1.835 based on 209 comparisons.

The reliability factor for the hot channel peaking factor calculated according to the above procedure is RF7g = .046.

Nevertheless, the more conservative RF 7g = 0.057 documented in Section 3.7.2 of MSS-NAl-P will be used in safety related analyses.

t

MSS-NAl-P Sucolement 1 Pace 39

4. MODEL APPLICATIONS TO REACTOR OPERATIONS The methods used in applying the reliability factors and biases to reactor operations support in the areas of startup testing, power distribution monitoring, and isotopic inventory are described in Section 4 of MSS-NAl-P.

l l

MSS-NAl-P Supplement 1 Pace 40

5. MODEL APPLICATIONS TO SAFETY EVALUATIONS The application of reliability factors and biases to the results of safety related physics calculations of F, g Fg, control rod worths, moderator temperature coefficient, fuel temperature coefficient, boron coefficient, effective delayed neutron fraction, prompt neutron generation time, shutdown margin, and scram worth vs. time is identical to that presented in Section 5 of MSS-NAl-P.

t _ - ---- -- -

MSS-NAl-P Supolement 1 Pace 41

6. REFERENCES

1. Letter, Robert A. Clark, NRC, to W. Cavanaugh III, AP&L, 08/11/82, File: 038-40.

2. Qualification of Reactor Physics Methods for ADolication to Pressurized Water Reactors of the Middle South Utilities System, MSS-NAl-P, 08/04/80.

3. Advanced Recycle Methodoloav Procram (ARMP) System Documentation, CCM-3 Research Project 118-1, September 1977.

4. Letter, D. C. Trimble, AP&L, to R. A. Clark, NRC, " Reactor Physics Methods MSS-NAl-P," 2CAN108107, 10/16/81, File: 038-40.

5. Owen, D. B., and R. E. Odeh, Tables for Normal Tolerance Limits. Samolina Plans, and Screenina, Marcel Dekker, Inc.,

1980.

MSS-NAl-P Sucolement 1 Pace 42

7. APPENDIX A TYPICAL WSES-3 POWER DISTRIBUTION COMPARISONS.

6 i i

1l liIl 41 1 8 57 8 0 1 3 0 1 1 11 3 -

4 e

g 2 7 2 9 6 3 0 5 0 a 5 6' 8 9 1 3 5 6 8 P 1 1 1 1 1 76 1 63 1 81 5 22 9 4 9 37 3 5 6 8 9 1 3 4 6 7 9 2 0 1 1 11 1 1 1 13 4 6 0 5 0 7 4 1 8 3 8 2 4 2 3 5 6 8 9 1 3 4 6 7 9 0 1 1 1 1 1 1 2 D 35 3 52 9 49 9 62 3 05 7 27 7 10 3 3 P 1 2 3 4 6 7 9 1 3 4 6 7 9 0 1 F 1 1 2 3 1 13 1 11 1 11 2 2 E - - -

2 2

2 2 4 8 3 8 5 2 9 6 1 6 0 2 2 T 1 2 3 4 6 7 9 1 2 4 6 7 9 0 1 A 1 1 1 1 1 1 2 2 S

E T

A 1 1 34 7 28 7 46 1 8 5 06 6

5 96 1 0

18 R 1 2 3 4 6 1

7 9 1 2 4 7 1

8 1 1 0 1 1 1 12 12 2 22 N 4 - - 7 1

O I' 2 I

C A

0 1

0 2 6 1 6

6 3 9

0 1

7 2

4 9 5

4 7

8 8

0 0

0 1

2 3 4 7 4 E 1 1 1 1 1 1 2 2 R 3 6 1

L 2 A<

95 9 16 5 02 5 2 9 65 3 85 3 70 9 96 Tt 1 3 4 6 7 9 0 2 4 5 7 8 9 0 0 0 1 1 10 1 10 1 12 1 23 m 2 - - - - - 5 N 1 2

I

. 8 8 0 4 9 4 1 8 5 2 7 2 6 8 8 C

I 1, 3 4 5 7 9 0 1

2 1

4 1

5 1

7 1

8 1

9 1

0 2

A 1 4 C 1 2

D N 73 7 90 3 86 3 03 7 49 1 66 1 52 7 71 A 1 1 2 3

4 5 2

7 9 0

0 1

2 10 4

1 5

12 7

1 8

12 9

1 0

22 S

A E

M 6 6 8 2 7 2 9 6 3 0 5 0 4 6 6 1 2 4 5 7 8 0 2 4 5 7 8 9 0 1 1 1 1 1 1 1 2 1

A E 57 5 73 1 69 1 85 5 24 9 42 9 31 5 55 R 1 2 4 5 7 8 0 2 3 5 6 8 11 9 0 U 1 0 1 0 1 10 1 10 1 1 23 G - - - -

I F

4 6 0 5 0 7 4 1 8 3 8 2 4 1 2 4 5 7 8 0 2 3 5 6 8 9 1 1 1 1 1 1 1 1 E R 12 t

n UR IE 54 2

9 3

40 5

9 6

66 8

3 0

00 2

7 3

24 5

7 6 8 e CB0 0 O 2 1 13 1 12 1 14 m I 0 - - - -

l e PW1 p

p FN* 6 1 6 u OX IP 8

3 3

5 8 5 8

2 0

9 1 3 5 6 1 1 S

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/

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- S-l A GSM IA( 30 0 7 47 N 8 0 1 3

- 3 1 1 11 S - -

S M

l l11l1ll

1l 11I1 , ' I1 i, llliIl lIl1 4

4 e

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+ + :

a P +..++++++++++*++++M++++M++++M++++M++++W++++M....

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.. P ..

.. P .

., P .

P

+., . ..

PM P

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P .. P ..

F .. P ..

E .. P ..

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.. P .

, .. P ..P 0 .. P M O 2 +...

P ..

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N .. P ..

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I .. P .

S .. P .

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. P ..

I' .. P ..

A .. P ..

R .. P ..

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E .. P ..

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f f

T .. P .

C .. P ..

G A +..

E ..

PM P

I E

R .. P ..

H

. P ..

. .. P ..

E C .. P ..

R I .. P .

O A .. P .

C C .. P .

P ..

D +..

. P ..

N .. P ..

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A .. P .

E .. P .

M . P .

.. P ..

2

+.. ..

PM P

. P ..

A .. P ..

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M E .. P .

I R P I T

U .. P .

O G .. P .

I .. P ..

B F +.. P .

. P ..

.. P ..

.. P .

1 .. P .

P ..

t n

+.. ..

PME e .. P ..

m s .. P ..

e .. P ..

l .. P ..

. P .

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.. P 9 P ..

P

+.. ..

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- H l 0 0 0 a

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Page 45 MSS-NAl-P Supplement 1 FIGURE A.3 MEAS. AND CAIC. REACTICN RA'IES SIRING 32, 22 EFPD

+ + + + + + + + + + +

....................... M M +

+ +

+ PPPPPPPP PPPPPPP M

1.60 M PPPPPP P M PP +

+ PPP PPPPP PM PPP +

+ P +

+ PPP PP +

+ PP PPIM ++

M P +

+ P PP

+ PP PP +

+ P +

P +

+ P PPP ++

1.20 M P PP +

+ PP P +

+ P PP +

+ P P +

+ P P M M P P +

+ M PP +

+ P +

+ P M +

+ P P M 0.80 M P P +

+ P + i

+ P P + '

+ P P +

+ P P M M P P +

+ P +

+P P+

+P P++

0.40 M +

+ +

+

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.....................................................................................M.

l B0rltM 00RE HEIGHT 'IOP i

i I

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Page 46 MSS-NAl-P Supplement 1 FIGURE A.4 MEAS. AND CAI.C. RDCTICN RA3ES SIRING 39, 22 EFPD

+ + + + + + + + +

+ + ...................................................................,.............

M 1.60 M +

+ +

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+ M PPPPP M -

M INPP P + 1

+ P PPP PPP PP + !

+ PP +

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+ P +

+ P P PPP +

+ P P +

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++ P PP +

+ P P +

+ MP PP +

+ P PP M 0.80 M P P +

[

+ P MP +

l

+ P P +

l + P P +

1 + P P M M P P +

+ +

P

+ P P +

+P PM 0.40 ++P PF

+ +

+ M l M +

+ +

+

0.0 M. . . ... ...... . .......... ................. ........................................................M.

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4 1 9 6 1 6 0 2 2 2 2 4 8 3 8 5 2 1 2 4 6 7 9 0 1 T 1 2 3 4 6 7 9 1 1 1 1 1 2 2 A 1 S

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'A 1 1 38 7 21 7 42 1 83 5 04 5 99 1 10 6 7 9 2 4 6 7 8 0 1 P 1 2 3 1

4 1 0 1

1 10 1 12 1 11 2 21

- 7 H

C 4 - -

1 I 2 T

C 0 0 2 6 1 6 3 0 7 4 9 4 8 0 0 A 1 2 3 4 6 7 9 1 2 4 5 7 8 0 1 E 1 1 1 1 1 1 2 2 6

R 3 1 L 2 A 04 5 22 9 67 3 84 3 75 9 95 R 97 9 15 5 8 9 0 1 3 4 6 7 9 0 2 4 5 7 E 0 0 0 1 1 10 1 10 1 11 1 22 T 2 - - - - - - 5 L.

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4 0 0 1 11 1 12 1 11 1 20 S

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A E 51 5 72 1 60 1 83 5 23 9 41 9 38 5 56 5 7 8 0 2 3 5 6 8 9 0 R 1 2 4 1 10 1 10 1 20 U 1 0 1 0 1 10 G - - -

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4 6 0 5 0 7 4 1 8 3 8 2 4 1 2 4 5 7 8 0 2 3 5 6 8 9 1 1 1 1 1 1 1 1 E R 9 64 3 08 7 22 7 14 t

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43 5 6 8 0 2 3 5 6 8 e 1 11 1 10 1 11 n CB0 1 0 1 a IM0 P 1 l

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Page 49 PES-lal-P Sumlement 1 FIGURE A.7 MEAS. AND CAIC. REACI'ICH RATES SIRING 32,146 EFPD

+ + + + + + + + + + +

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

1. 60 ++ +

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PPPP M PPPPIM ++

++ +

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P +

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I l

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1.20 ++ P P +

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+ M MP +

+ P P +

+ P P H 0.80 ++ +

+ PP P +

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+ P P ++

++ +

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+ +

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C G .. P ..

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MSS-NAl-P Stsplement 1 - 14mga 53 FIGURE A.11 MEAS. AND CAIC. REAC1'ICN RA'IES STRING 32, 261 EFPD

+ + + +. + + +

+ + + +

s .s s ..s ... s . s e a s ...........s

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s s ....

1.60

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+ +

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M

+ +

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! + PPP PPPPPPPP PPPPPPPPPP P +

+ PPP M PPP PPPPP PEMPPPPPPP PPP +

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+ P P +

+ P MP +

1

+ P P +

J + P P +

i

PM M

+ P P +

1 + P +

j + P P +

+ P P +

0.80 M P 4e

+ P +

+ P P+

+P +

l

++P Pt+

+ +

i 4 + +

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l

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+ +

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Page 54 ISS-NAl-P Suppleasent 1 FIGURE A.12 MEAS. AND CAIC. REACTICN RATES STRING 39, 261 EFPD

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+P +

+ +

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+ +

+

H +

+

0.0 H. .... . ,. . .. ... .. .... . .. ... .. , .. , ,. . . ...... .. .. .

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