NOC-AE-21003795, Cycle 22 Core Operating Limits Report

Cycle 22 Core Operating Limits Report

ML21105A843
Person / Time
Site:	South Texas
Issue date:	04/15/2021
From:	Georgeson C South Texas
To:	Document Control Desk, Office of Nuclear Reactor Regulation
References
35152704, NOC-AE-21003795
Download: ML21105A843 (19)

Text

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Nuclear Operating Company South Texas f'ro/ect Electrlc Ge11erall11g Stat/011 P.O. Bax 28fJ /Mldswort/J, Texas 7748]

April 15, 2021 NOC-AE-21003795 10 CFR 50.36 STI: 35152704 ATTN: Document Control Desk U.S. Nuclear Regulatory Commission Washington, DC 20555-0001 South Texas Project Unit 2 Docket No. STN 50-499 Unit 2 Cycle 22 Core Operating Limits Report In accordance with Technical Specification 6.9.1.6.d, STP Nuclear Operating Company submits the attached Core Operating Limits Report (COLR) for Unit 2 Cycle 22. The report covers the core design changes made during the 2RE21 refueling outage.

There are no commitments in this letter.

If there are any questions regarding this report, please contact Zachary Dibbern at (361) 972-4336 or me at (361) 972-7806.

~~

Christopher H. Georgeson General Manager, Engineering

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South Texas Project Unit 2 Cycle 22 Core Operating Limits Report, Revision 0 cc; Regional Administrator, Region IV U.S. Nuclear Regulatory Commission 1600 E. Lamar Boulevard Arlington, TX 76011-4511

NOC-AE-21003795 Attachment Attachment South Texas Project Unit 2 Cycle 22 Core Operating Limits Report, Revision 0

SOUTH TEXAS PROJECT Unit 2 Cycle 22 CORE OPERATING LIMITS REPORT U2C22-0 Revision 0 Core Operating Limits Report Page 1 of 17

Unit 2 Cycle 22 Core Operating Limits Report Rev. 0 Page 2 of 17 1.0 CORE OPERATING LIMITS REPORT This Core Operating Limits Report for STPEGS Unit 2 Cycle 22 has been prepared in accordance with the requirements of Technical Specification 6.9.1.6. The core operating limits have been developed using the NRC-approved methodologies specified in Technical Specification 6.9.1.6.

The Technical Specifications affected by this report are:

1) 2.1 SAFETY LIMITS

2) 2.2 LIMITING SAFETY SYSTEM SETTINGS

3) 3/4.1.1.1 SHUTDOWN MARGIN

4) 3/4.1.1.3 MODERATOR TEMPERATURE COEFFICIENT LIMITS

5) 3/4.1.3.5 SHUTDOWN ROD INSERTION LIMITS

6) 3/4.1.3.6 CONTROL ROD INSERTION LIMITS

7) 3/4.2.1 AFD LIMITS

8) 3/4.2.2 HEAT FLUX HOT CHANNEL FACTOR

9) 3/4.2.3 NUCLEAR ENTHALPY RISE HOT CHANNEL FACTOR

10) 3/4.2.5 DNB PARAMETERS 2.0 OPERATING LIMITS The cycle-specific parameter limits for the specifications listed in Section 1.0 are presented below.

2.1 SAFETY LIMITS (Specification 2.1):

2.1.1 The combination of THERMAL POWER, pressurizer pressure, and the highest operating loop coolant temperature (T avg ) shall not exceed the limits shown in Figure 1.

2.2 LIMITING SAFETY SYSTEM SETTINGS (Specification 2.2):

2.2.1 The Loop design flow for Reactor Coolant Flow-Low is 98,000 gpm.

Unit 2 Cycle 22 Core Operating Limits Report Rev. 0 Page 3 of 17 2.2.2 The Over-temperature T and Over-power T setpoint parameter values are listed below:

Over-temperature T Setpoint Parameter Values 1 measured reactor vessel T lead/lag time constant, 1 = 8 sec 2 measured reactor vessel T lead/lag time constant, 2 = 3 sec 3 measured reactor vessel T lag time constant, 3 = 2 sec 4 measured reactor vessel average temperature lead/lag time constant, 4 = 28 sec 5 measured reactor vessel average temperature lead/lag time constant, 5 = 4 sec 6 measured reactor vessel average temperature lag time constant, 6 = 2 sec K 1 Overtemperature T reactor trip setpoint, K1 = 1.14 K 2 Overtemperature T reactor trip setpoint T avg coefficient, K2 = 0.028/°F K 3 Overtemperature T reactor trip setpoint pressure coefficient, K3 = 0.00143/psi T Nominal full power T avg , T 592.0 °F P Nominal RCS pressure, P = 2235 psig f 1 (I) is a function of the indicated difference between top and bottom detectors of the power-range neutron ion chambers; with gains to be selected based on measured instrument response during plant startup tests such that:

(1) For q t - q b between -70% and +8%, f 1 (I) = 0, where q t and q b are percent RATED THERMAL POWER in the top and bottom halves of the core respectively, and q t + q b is total THERMAL POWER in percent of RATED THERMAL POWER; (2) For each percent that q t - q b is more negative than -70%, the T Trip Setpoint shall be automatically reduced by 0.0% of its value at RATED THERMAL POWER; and (3) For each percent that q t - q b is more positive than +8%, the T Trip Setpoint shall be automatically reduced by 2.65% of its value at RATED THERMAL POWER.

(Reference 3.6 and Section 4.4.1.2 of Reference 3.7)

Over-power T Setpoint Parameter Values 1 measured reactor vessel T lead/lag time constant, 1 = 8 sec 2 measured reactor vessel T lead/lag time constant, 2 = 3 sec 3 measured reactor vessel T lag time constant, 3 = 2 sec 6 measured reactor vessel average temperature lag time constant, 6 = 2 sec 7 Time constant utilized in the rate-lag compensator for T avg , 7 = 10 sec K4 Overpower T reactor trip setpoint, K4 = 1.08 K5 Overpower T reactor trip setpoint Tavg rate/lag coefficient, K 5 = 0.02/°F for increasing average temperature, and K 5 = 0 for decreasing average temperature K6 Overpower T reactor trip setpoint Tavg heatup coefficient K 6 = 0.002/°F for T > T, and K 6 = 0 for T T T Indicated full power T avg , T 592.0 °F f 2 (I) = 0 for all (I)

Unit 2 Cycle 22 Core Operating Limits Report Rev. 0 Page 4 of 17 2.3 SHUTDOWN MARGIN (Specification 3.1.1.1):

The SHUTDOWN MARGIN shall be:

2.3.1 Greater than 1.3% for MODES 1 and 2*

• See Special Test Exception 3.10.1 2.3.2 Greater than the limits in Figure 2 for MODES 3 and 4.

2.3.3 Greater than the limits in Figure 3 for MODE 5.

2.4 MODERATOR TEMPERATURE COEFFICIENT (Specification 3.1.1.3):

2.4.1 The BOL, ARO, MTC shall be less positive than the limits shown in Figure 4.

2.4.2 The EOL, ARO, HFP, MTC shall be less negative than -62.6 pcm/°F.

2.4.3 The 300 ppm, ARO, HFP, MTC shall be less negative than -53.6 pcm/°F (300 ppm Surveillance Limit).

Where: BOL stands for Beginning-of-Cycle Life, EOL stands for End-of-Cycle Life, ARO stands for All Rods Out, HFP stands for Hot Full Power (100% RATED THERMAL POWER),

HFP vessel average temperature is 592 °F.

2.4.4 The Revised Predicted near-EOL 300 ppm MTC shall be calculated using the algorithm from the document referenced by Technical Specification 6.9.1.6.b.10:

Revised Predicted MTC = Predicted MTC + AFD Correction - 3 pcm/°F If the Revised Predicted MTC is less negative than the COLR Section 2.4.3 limit and all of the benchmark data contained in the surveillance procedure are met, then an MTC measurement in accordance with S.R. 4.1.1.3b is not required.

2.5 ROD INSERTION LIMITS (Specification 3.1.3.5 and 3.1.3.6):

2.5.1 All banks shall have the same Full Out Position (FOP) of either 255 or 259 steps withdrawn.

2.5.2 The Control Banks shall be limited in physical insertion as specified in Figure 5.

2.5.3 Individual Shutdown bank rods are fully withdrawn when the Bank Demand Indication is at the FOP and the Rod Group Height Limiting Condition for Operation is satisfied (T.S. 3.1.3.1).

Unit 2 Cycle 22 Core Operating Limits Report Rev. 0 Page 5 of 17 2.6 AXIAL FLUX DIFFERENCE (Specification 3.2.1):

2.6.1 AFD limits as required by Technical Specification 3.2.1 are determined by Constant Axial Offset Control (CAOC) Operations with an AFD target band of +5, -10%.

2.6.2 The AFD shall be maintained within the ACCEPTABLE OPERATION portion of Figure 6, as required by Technical Specifications.

2.7 HEAT FLUX HOT CHANNEL FACTOR (Specification 3.2.2):

2.7.1 FRTP Q = 2.55.

2.7.2 K(Z) is provided in Figure 7.

2.7.3 The F xy limits for RATED THERMAL POWER (FRTP xy ) within specific core planes shall be:

2.7.3.1 Less than or equal to 2.102 for all cycle burnups for all core planes containing Bank "D" control rods, and 2.7.3.2 Less than or equal to the appropriate core height-dependent value from Table 1 for all unrodded core planes.

2.7.3.3 PF xy = 0.2.

These F xy limits were used to confirm that the heat flux hot channel factor F Q (Z) will be limited by Technical Specification 3.2.2 assuming the most-limiting axial power distributions expected to result for the insertion and removal of Control Banks C and D during operation, including the accompanying variations in the axial xenon and power distributions, as described in WCAP-8385. Therefore, these F xy limits provide assurance that the initial conditions assumed in the LOCA analysis are met, along with the ECCS acceptance criteria of 10 CFR 50.46.

2.7.4 The F xy limits from Section 2.7.3 above are not applicable in the following core plane regions:

2.7.4.1 Upper and lower core plane regions as presented in Table 2, and 2.7.4.2 Grid plane regions as presented in Table 2, and 2.7.4.3 Core plane regions within +/- 2% of core height (+/- 3.36 inches) about the bank demand position of the bank D control rods.

2.7.5 Core Power Distribution Measurement Uncertainty for the Heat Flux Hot Channel Factor 2.7.5.1 If the Power Distribution Monitoring System (PDMS) is operable, as defined in the Technical Requirements Manual Section 3.3.3.12, the core power distribution measurement uncertainty (U FQ ) to be applied to the F Q (Z) and F xy (Z) using the PDMS shall be calculated by:

U FQ = (1.0 + (U Q /100))*U E Where:

Unit 2 Cycle 22 Core Operating Limits Report Rev. 0 Page 6 of 17 U Q = Uncertainty for power peaking factor as defined in Equation 5-19 from the document referenced by Technical Specification 6.9.1.6.b.11 U E = Engineering uncertainty factor of 1.03.

This uncertainty is calculated and applied automatically by the Power Distribution Monitoring System (PDMS).

2.7.5.2 If the moveable detector system is used, the core power distribution measurement uncertainty (U FQ ) to be applied to the F Q (Z) and F xy (Z) shall be calculated by:

U FQ = U QU *U E Where:

U QU = Base F Q measurement uncertainty of 1.05.

U E = Engineering uncertainty factor of 1.03.

2.8 ENTHALPY RISE HOT CHANNEL FACTOR (Specification 3.2.3):

2.8.1 FRTP H = 1.62 2.8.2 PF H = 0.3 2.8.3 Core Power Distribution Measurement Uncertainty for the Enthalpy Rise Hot Channel Factor 2.8.3.1 If the Power Distribution Monitoring System (PDMS) is operable, as defined in the Technical Requirements Manual Section 3.3.3.12, the core power distribution measurement uncertainty (U FH ) to be applied to the FNH using the PDMS shall be the greater of:

U FH = 1.04 OR U FH = 1.0 + (U H /100)

Where:

U H = Uncertainty for power peaking factor as defined in Equation 5-19 from the document referenced in Technical Specification 6.9.1.6.b.11.

This uncertainty is calculated and applied automatically by the Power Distribution Monitoring System.

2.8.3.2 If the moveable detector system is used, the core power distribution measurement uncertainty (U FH ) shall be:

U FH = 1.04

Unit 2 Cycle 22 Core Operating Limits Report Rev. 0 Page 7 of 17 2.9 DNB PARAMETERS (Specification 3.2.5):

2.9.1 The following DNB-related parameters shall be maintained within the following limits (nominal values from Reference 3.1, as annotated below): 1 2.9.1.1 Reactor Coolant System T avg 595 °F 2, 2.9.1.2 Pressurizer Pressure > 2200 psig 3, 2.9.1.3 Minimum Measured Reactor Coolant System Flow > 403,000 gpm4.

3.0 REFERENCES

3.1 Letter from A. S. Ganey (Westinghouse) to. F. Yilmaz (STPNOC), "South Texas Project Electric Generating Station Unit 2 Cycle 22 Final Reload Evaluation" NF-TG-20-049 (ST-UB-NOC-20000038) dated January 5, 2021.

3.2 NUREG-1346, Technical Specifications, South Texas Project Unit Nos. 1 and 2.

3.3 STPNOC Calculation ZC-7035, Rev. 2, Loop Uncertainty Calculation for RCS Tavg Instrumentation, Section 10.1.

3.4 STPNOC Calculation ZC-7032, Rev. 6, Loop Uncertainty Calculation for Narrow Range Pressurizer Pressure Monitoring Instrumentation, Section 2.3, Page 9.

3.5 Letter from J. S Wyble (Westinghouse) to T. J. Jordan (STPNOC), STP Nuclear Operating Company Units 1 & 2 Power Uprate PCWG Parameters, ST-WN-NOC-00-000072 dated December 15, 2000, STI 31218644.

3.6 Letter from J. M. Ralston (Westinghouse) to D. F. Hoppes (STPNOC), South Texas Project Electric Generating Station Units 1 and 2 Documentation of the f 1 (I) Function in OTT Setpoint Calculation, NF-TG-11-93 (ST-UB-NOC-11003215) dated November 10, 2011.

3.7 Document RSE-U2, Rev. 10, Unit 2 Cycle 22 Reload Safety Evaluation and Core Operating Limits Report. (CR Action 19-9842-55) 1 A discussion of the processes to be used to take these readings is provided in the basis for Technical Specification 3.2.5.

2 Includes a 1.9 °F measurement uncertainty per Reference 3.3, Page 37.

3 Limit not applicable during either a Thermal Power ramp in excess of 5% of RTP per minute or a Thermal Power step in excess of 10% RTP. Per Technical Specification 3.2.5 Bases, this includes a 10.7 psi measurement uncertainty as read on the QDPS display, which when added to the safety analysis limit of 2189 psig gives the COLR limit listed above.

The 10.7 psi uncertainty is bounded by the 9.6 psi averaged measurement calculated in Reference 3.4.

4 Includes the flow measurement uncertainty of 2.8% from Reference 3.5.

Unit 2 Cycle 22 Core Operating Limits Report Rev. 0 Page 8 of 17 Figure 1 Reactor Core Safety Limits - Four Loops in Operation 680

( 2 , 664.52 )

Unacceptable 660

( 2 , 652.10 )

2450 PSIA

( 96 , 638.57 )

640 2250 PSIA

( 2 , 622.54 )

620 ( 102 , 622.62 )

RCS Tavg (°F) 1830 PSIA ( 130 , 600.11 )

600

( 130 , 589.08 )

( 112 , 587.35 )

580 Acceptable 560 ( 130 , 563.93 )

540 0 20 40 60 80 100 120 140 Rated Thermal Power (%)

Unit 2 Cycle 22 Core Operating Limits Report Rev. 0 Page 9 of 17 Figure 2 Required Shutdown Margin for Modes 3 & 4 7.0 6.0 Acceptable ( 2400 , 5.15 )

5.0 Required Shutdown Margin (% Delta Rho) 4.0 3.0 2.0

( 0 , 1.30 )

Unacceptable

( 600 , 1.30 )

1.0 0.0 0 400 800 1200 1600 2000 2400 RCS Critical Boron Concentration (ppm)

(for ARI minus most reactive stuck rod)

Unit 2 Cycle 22 Core Operating Limits Report Rev. 0 Page 10 of 17 Figure 3 Required Shutdown Margin for Mode 5 7.0 6.0 Acceptable 5.0 Required Shutdown Margin (% Delta Rho)

( 2400 , 4.50 )

4.0 3.0 2.0

( 0 , 1.30 )

Unacceptable

( 650 , 1.30 )

1.0 0.0 0 400 800 1200 1600 2000 2400 RCS Critical Boron Concentration (ppm)

(for ARI minus most reactive stuck rod)

Unit 2 Cycle 22 Core Operating Limits Report Rev. 0 Page 11 of 17 Figure 4 MTC versus Power Level 7.0 6.0 Unacceptable 5.0 4.0 Moderator Temperature Coefficient (pcm/°F)

Acceptable 3.0 2.0 1.0 0.0

-1.0

-2.0

-3.0 0 10 20 30 40 50 60 70 80 90 100 Rated Thermal Power (%)

Unit 2 Cycle 22 Core Operating Limits Report Rev. 0 Page 12 of 17 Figure 5 Control Rod Insertion Limits* versus Power Level 260

( 23 , 259 ): 122 Step Overlap ( 79 , 259 ): 122 Step Overlap

( 21 , 255 ): 118 Step Overlap ( 77 , 255 ): 118 Step Overlap 240 220 Bank B 200 ( 0 , 202 )

180

( 100 , 174 )

160 Bank C Rod Group Position (Steps) 140 120 100 Bank D 80 60 ( 0 , 65 )

40 20

• Control Bank A is already withdrawn to Full Out Position.

Fully withdrawn shall be the condition where shutdown and

( 29 , 0 ) control banks are at the position of either 255 or 259 steps withdrawn.

0 0 10 20 30 40 50 60 70 80 90 100 Rated Thermal Power (%)

Unit 2 Cycle 22 Core Operating Limits Report Rev. 0 Page 13 of 17 Figure 6 AFD Limits versus Power Level 120 110 100

( -11 , 90 ) ( 11 , 90 )

90 80 Unacceptable Unacceptable Rated Thermal Power (%)

70 Acceptable 60 50

( -31 , 50 ) ( 31 , 50 )

40 30 20 10 0

-50 -40 -30 -20 -10 0 10 20 30 40 50 Axial Flux Difference (% Delta-I)

Unit 2 Cycle 22 Core Operating Limits Report Rev. 0 Page 14 of 17

Unit 2 Cycle 22 Core Operating Limits Report Rev. 0 Page 15 of 17 Table 1 (Part 1 of 2)

Unrodded F xy for Each Core Height for Cycle Burnups Less Than 10000 MWD/MTU (Subject to the exclusion zones of COLR Section 2.7.4)

Core Height Axial Unrodded Core Height Axial Unrodded (Ft.) Point Fxy (Ft.) Point Fxy 14.0 1 7.136 6.8 37 1.913 13.8 2 5.558 6.6 38 1.969 13.6 3 3.983 6.4 39 1.946 13.4 4 2.640 6.2 40 1.893 13.2 5 2.456 6.0 41 1.853 13.0 6 2.183 5.8 42 1.882 12.8 7 2.105 5.6 43 1.899 12.6 8 2.115 5.4 44 1.903 12.4 9 2.080 5.2 45 1.951 12.2 10 2.024 5.0 46 2.025 12.0 11 1.986 4.8 47 2.051 11.8 12 1.999 4.6 48 2.001 11.6 13 2.045 4.4 49 1.934 11.4 14 2.034 4.2 50 1.944 11.2 15 1.984 4.0 51 1.953 11.0 16 1.951 3.8 52 1.944 10.8 17 1.945 3.6 53 1.958 10.6 18 1.935 3.4 54 2.015 10.4 19 1.922 3.2 55 2.051 10.2 20 1.944 3.0 56 1.998 10.0 21 1.978 2.8 57 1.948 9.8 22 1.985 2.6 58 1.954 9.6 23 1.919 2.4 59 1.961 9.4 24 1.887 2.2 60 1.955 9.2 25 1.888 2.0 61 1.958 9.0 26 1.870 1.8 62 1.987 8.8 27 1.869 1.6 63 1.989 8.6 28 1.886 1.4 64 1.899 8.4 29 1.950 1.2 65 1.831 8.2 30 2.011 1.0 66 1.862 8.0 31 1.955 0.8 67 2.166 7.8 32 1.889 0.6 68 2.904 7.6 33 1.867 0.4 69 4.151 7.4 34 1.883 0.2 70 5.907 7.2 35 1.881 0.0 71 8.818 7.0 36 1.867

Unit 2 Cycle 22 Core Operating Limits Report Rev. 0 Page 16 of 17 Table 1 (Part 2 of 2)

Unrodded Fxy for Each Core Height for Cycle Burnups Greater Than or Equal to 10000 MWD/MTU (Subject to the exclusion zones of COLR Section 2.7.4)

Core Height Axial Unrodded Core Height Axial Unrodded (Ft.) Point Fxy (Ft.) Point Fxy 14.00 1 6.364 6.80 37 2.195 13.80 2 5.077 6.60 38 2.249 13.60 3 3.790 6.40 39 2.217 13.40 4 2.690 6.20 40 2.150 13.20 5 2.548 6.00 41 2.113 13.00 6 2.277 5.80 42 2.104 12.80 7 2.119 5.60 43 2.092 12.60 8 2.060 5.40 44 2.076 12.40 9 2.003 5.20 45 2.096 12.20 10 1.981 5.00 46 2.137 12.00 11 1.988 4.80 47 2.134 11.80 12 2.019 4.60 48 2.073 11.60 13 2.068 4.40 49 2.023 11.40 14 2.060 4.20 50 2.017 11.20 15 2.021 4.00 51 2.005 11.00 16 1.980 3.80 52 1.989 10.80 17 2.007 3.60 53 1.992 10.60 18 2.015 3.40 54 2.031 10.40 19 2.017 3.20 55 2.059 10.20 20 2.052 3.00 56 2.001 10.00 21 2.112 2.80 57 1.942 9.80 22 2.140 2.60 58 1.913 9.60 23 2.099 2.40 59 1.885 9.40 24 2.064 2.20 60 1.872 9.20 25 2.080 2.00 61 1.880 9.00 26 2.092 1.80 62 1.924 8.80 27 2.096 1.60 63 1.950 8.60 28 2.107 1.40 64 1.926 8.40 29 2.154 1.20 65 1.936 8.20 30 2.199 1.00 66 2.041 8.00 31 2.156 0.80 67 2.398 7.80 32 2.115 0.60 68 3.112 7.60 33 2.115 0.40 69 4.195 7.40 34 2.125 0.20 70 5.678 7.20 35 2.133 0.00 71 8.314 7.00 36 2.141

Unit 2 Cycle 22 Core Operating Limits Report Rev. 0 Page 17 of 17 Table 2 Core and Grid Plane Fxy Exclusion Zones Core Core Core Core Axial Height Height Axial Height Height Point (in.) (%) Top/Bottom Grid Point (in.) (%) Top/Bottom Grid 1 168.0 100.0 Excluded 37 81.6 48.6 2 165.6 98.6 Excluded 38 79.2 47.1 Excluded 3 163.2 97.1 Excluded 39 76.8 45.7 Excluded 4 160.8 95.7 Excluded 40 74.4 44.3 5 158.4 94.3 Excluded Excluded 41 72.0 42.9 6 156.0 92.9 Excluded Excluded 42 69.6 41.4 7 153.6 91.4 Excluded 43 67.2 40.0 8 151.2 90.0 Excluded 44 64.8 38.6 9 148.8 88.6 45 62.4 37.1 10 146.4 87.1 46 60.0 35.7 Excluded 11 144.0 85.7 47 57.6 34.3 Excluded 12 141.6 84.3 48 55.2 32.9 Excluded 13 139.2 82.9 Excluded 49 52.8 31.4 14 136.8 81.4 Excluded 50 50.4 30.0 15 134.4 80.0 Excluded 51 48.0 28.6 16 132.0 78.6 52 45.6 27.1 17 129.6 77.1 53 43.2 25.7 18 127.2 75.7 54 40.8 24.3 Excluded 19 124.8 74.3 55 38.4 22.9 Excluded 20 122.4 72.9 56 36.0 21.4 Excluded 21 120.0 71.4 Excluded 57 33.6 20.0 22 117.6 70.0 Excluded 58 31.2 18.6 23 115.2 68.6 Excluded 59 28.8 17.1 24 112.8 67.1 60 26.4 15.7 25 110.4 65.7 61 24.0 14.3 26 108.0 64.3 62 21.6 12.9 Excluded 27 105.6 62.9 63 19.2 11.4 Excluded 28 103.2 61.4 64 16.8 10.0 Excluded Excluded 29 100.8 60.0 Excluded 65 14.4 8.6 Excluded 30 98.4 58.6 Excluded 66 12.0 7.1 Excluded 31 96.0 57.1 Excluded 67 9.6 5.7 Excluded 32 93.6 55.7 68 7.2 4.3 Excluded 33 91.2 54.3 69 4.8 2.9 Excluded Excluded 34 88.8 52.9 70 2.4 1.4 Excluded Excluded 35 86.4 51.4 71 0.0 0.0 Excluded Excluded 36 84.0 50.0