ML24304B051

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Cycle 26 Core Operating Limits Report
ML24304B051
Person / Time
Site: South Texas STP Nuclear Operating Company icon.png
Issue date: 10/30/2024
From: Georgeson C
South Texas Electric Cooperative
To:
Office of Nuclear Reactor Regulation, Document Control Desk
References
NOC-AE-24004077, STI: 35661032
Download: ML24304B051 (1)
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Text

{{#Wiki_filter:m: October 30,2024 NOC-AE-24004077 10 cFR 50.36 STI: 35661032 ATTN: Document Control Desk U.S. Nuclear Regulatory Commission Washington, DC 20555-0001 South Texas Project Unit 1 Docket No. STN 50-498 Unit 1 Cvcle 26 Core Operatinq Limits Report ln accordance with Technical Specification 6.9.1.6.d, STP Nuclear Operating Company submits the attached Core Operating Limits Report (COLR) for Unit 1 Cycle 26. The report covers the core design changes made during the 1RE25 refueling outage. There are no commitments in this letter lf there are any questions regarding this report, please contact Derrick Johnson at (361) 972-7088 or me at (361) 972-7806. l,/ Christopher H Gen Mgr Strategic Proj & Eng Design drj

Attachment:

South Texas Project Unit 1 Cycle 26 Core Operating Limits Report, Revision 0 Regional Administrator, Region lV U.S. Nuclear Regulatory Commission 1600 E. Lamar Boulevard Arlington, TX 7601 1-4511 cc:

NOC-AE-24Q04077 Attachment Attachment South Texas Project Unit 1 Cycle 26 Core Operating Limits Report, Revision 0

Uf SOUTH TEXAS PROJECT Unit L Cycle 26 CORE OPERATING LIMITS REPORT ULC26.O Revision 0 Core Operating Limits Report Page I oflT

G']Ill Nu6l6ir Oper3tlng Coffipany

JT Unit 1 Cycle 26 Core Operating Limits Report u1c26-0 Rev.0 2of17 1.0 CORX, OPERATING LIMITS RE,PORT This Core Operating Limits Report for STPEGS Unit 1 Cycle 26has 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: l) 2.1 SAFETY LTMTTS

2) 2.2 LIMITING SAFETY SYSTEM SETTINGS
3) 314.1.1.t SHUTDOWN MARGTN
4) 314.1.1.3 MODERATOR TEMPERATURE COEFFTCTENT LrMrrS
5) 314.t.3.s SHUTDOWN ROD TNSERTTON LrMrrS
6) 314.1.3.6 CONTROL ROD TNSERTTON LTMTTS
7) 314.2.1 AFD LTMTTS
8) 314.2.2 HEAT FLUX HOT CHANNEL FACTOR
9) 314.2.3 NUCLEAR ENTHALPY RISE HOT CHANNEL FACTOR
10) 3/4.2.s DNB PARAMETERS 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*g) shall not exceed the limits shown in Figure 1 2.2 LIMITING SAFETY SYSTEM SETTINGS (Specification2.2): 2.2.1 The Loop design flow for Reactor Coolant Flow-Low is 98,000 gpm. 2.0

Gt[ Nuclear Operating Company Y:T Unit 1 Cycle 26 Core Operating Limits Report u1c26-0 Rev.0 Pase 3 of 17 2.2.2 The Over-temperature AT and Over-power AT setpoint parameter values are listed below: Over-temperature AT Setpoint Parameter Values r,1 measured reactor vessel AT lead/lag time constant, 'rr : 8 sec r,z measured reactor vessel AT lead/lag time constant, 'uz : 3 sec 't3 measured reactor vessel AT lag time constant, t3 : 2 sec ^c4 measured reactor vessel average temperature leadllag time constant, T4:28 sec r,s measured reactor vessel average temperature lead/lag time constant, T 5 : 4 sec x6 measured reactor vessel average temperature lag time constant, 16:2 sec Kr Overtemperature AT reactor trip setpoint, Kr : l.14 Kz Overtemperature AT reactor trip setpoint Tuug coeffrcient, Kz : 0.028/"F K: Overtemperature AT reactor trip setpoint pressure coefficient, K: : 0.00143/psi T' Nominal full power Tuug, T'< 592.0 "F P' Nominal RCS pressure, P' :2235 psig fr(AI) is a function ofthe indicated difference between top and bottom detectors ofthe power-range neutron ion chambers; with gains to be selected based on measured instrument response during plant startup tests such that: (1) For qt - qr between -70o/o and +8%, fr(Al) : 0, where q, and qu are percent RATED THERMAL POWER in the top and bottom halves of the core respectively, and qt + qb is total THERMAL POWER in percent of RATED THERMAL POWER; (2) For each percent that qr - qu is more negative than -70o/o, the AT Trip Setpoint shall be automatically reduced by 0.0% of its value at RATED THERMAL POWER; and (3) For each percent that the magnitude of qt - qu is more positive than+8%o, the AT 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 AT Setpoint Parameter Values 11 measured reactor vessel AT lead/lag time constant, T r : 8 sec rz measured reactor vessel AT lead/lag time constant, tz:3 sec r,3 measured reactor vessel AT lag time constant, t3 : 2 sec "E6 measured reactor vessel average temperature lag time constant, T6 : 2 sec r,7 Time constant utilized in the rate-lag compensator for Tuur, tz : l0 sec K+ Overpower AT reactor trip setpoint, K+ : 1.08 Ks Overpower AT reactor trip setpoint Taugrateflag coefficient, Ks : 0.02l'F for increasing average temperature, and Ks : 0 for decreasing average temperature Ke Overpower AT reactor trip setpoint Tuur heatup coefficient Ko : 0.002/oF for T ) T", and Ko:OforT < T" T" Indicated full power Tavs, T"< 592.0 'F fr(AI) : 0 for all (AI)

ry: Unit 1 Cycle26 Core Operating Limits Report u1c26-0 Rev 0 4of17 2.3 2.4 SHUTDOWN MARGIN1 (Specification 3.1.1.1): The SHUTDOWN MARGIN shall be: 2.3.1 Greaterthan 1.3% Lp foTMODES I and2*

  • 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. MODBRATOR TEMPERATURE COEFFICIBNT (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 4L6 pcml"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/oF If the Revised Predicted MTC is less negative than the COLR Section 2.4.3limitand 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. ROD INSERTION LIMITST (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 259,254, or 256 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). 2.5 t The Shutdown Margin and Rod Insertion Limits account for the removal of RCCA D6 in Shutdown Bank A.

U: Unit 1 Cycle26 Core Operating Limits Report atc26-0 Rev.0 Page 5 of 17 2.6 2.7 AXIAL FLUX DIFFBRENCE (Specification 3.2.1): 2.6.1 AFD limits as required by Technical Specification3.2.l 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. HEAT FLUX HOT CHANNEL FACTOR (Specification3.2.2)z 2.7.1 r$rP : z.ss. 2.7.2 K(Z) is provided in Figure 7. 2.7.3 The F, limits for RATED THERMAL POWER G$t) 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 Less than or equal to the appropriate core height-dependent value from Table I for all unrodded core planes. PFr:0.2. 2.7.3.2 2.7.3.3 2.7.4 2.7.5 These F, limits were used to confirm that the heat flux hot channel factor Fq(Z) will be limited by Technical Specification3.2.2 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,q, 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. The F, 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%o of core height (+ 3.36 inches) about the bank demand position of the bank'oD" control rods. 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 3.3.3.72, the core power distribution measurement uncertainty (Unq) to be applied to the Fq(Z) and Fr(Z) using the PDMS shall be calculated by: urQ: (1.0 + (uq/100))*un Where:

Unit 1 Cycle 26 Core Operafing Limits Report u1c26-0 Rev.0 U' 6of17 2.7.s.2 Ue: Uncertainty for power peaking factor as defined in Equation 5-19 from the document referenced by Technical Specification 6.9.1.6.b.1 1 LJE: Engineering uncertainty factor of 1.03. This uncertainty is calculated and applied automatically by the Power Distribution Monitoring System (PDMS). If the moveable detector system is used, the core power distribution measurement uncertainty (Ueq) to be applied to the Fq(Z) and Fr(Z) shall be calculated by: Une: Uqu*Un Where: Uqu : Base Fq measurement uncertainty of 1.05. Ue : Engineering uncertainty factor of 1.03. 2.8 BNTHALPY RISE HOT CHANNBL FACTOR (Specification 3.2.3): FIfr' : 1.62 PFas : 0.3 Core Power Distribution Measurement Uncertainty for the Enthalpy Rise Hot Channel Factor 2.8.3.1 Ifthe 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 (Uuu) to be applied to the FX" using the PDMS shall be the greater of: Unau: 1.04 OR IJpaH=1.0+(UaH/100) Where: UrH : Uncertainty for power peaking factor as defined in Equation 5-19 from the document referenced in Technical Specification 6.9.1.6.b.1 1. 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 (Uuu) shall be: 2.8.1 2.8.2 2.8.3 Unm: 1.04

Unit I Cycle26 Core Operating Limits Report ulc26-0 Rev.0 U: 7 of17 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): I 2.9.1.1 Reactor Coolant System Tuug 5 595 oF 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 Brown, P.A. (Westinghouse) to Aucoin, K. (STPNOC), "South Texas Project Electric Generating Station Unit 1 Cycle 26 Frnal Reload Evaluation" NF-TG-24-042 (ST-UB-NOC-24000030) dated August l, 2024. 3.2 NIIREG-1346, Technical Specifications, South Texas Project Unit Nos. I and2. 3.3 STPNOC Calculation ZC-07035,Rev. 3, "Loop Uncerlainty Calculation for RCS Tavg Instrumentation," Section 10.1. (STI: 35343289) 3.4 STPNOC Calculation ZC-07032, Rev. 7, "Loop Uncertainty Calculation forNarrow Range Pressurizer Pressure Monitoring Instrumentation," Section2.3,Page 9. (STI: 35191115) 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 1 5, 2000. (STI: 3 1218644) 3.6 Leffer from J. M. Ralston (Westinghouse) to D. F. Hoppes (STPNOC), "South Texas Project Electric Generating Station Units I and 2 Documentation of the fi(AI) Function in OTAT Setpoint Calculation," NF-TG-l 1-93 (ST-UB-NOC-1 1003215) dated November 1 0,2011. (STI: 33079478) 3.7 Document RSE-UI, Rev. 15, "Unit I Cycle 26 Reload Safety Evaluation and Core Operating Limits Report." (CR Action 23-2461-48) A discussion of the processes to be used to take these readings is provided in the basis for Technical Specification3.2.5. Includes a 1.9 "F measurement uncertainty per Reference 3.3,Page 37. 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 uncefiainty 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 uncerlainty calculated in Reference 3.4. Includes the most limiting flow measurement unceftainty of 2.8Yo from Reference 3.5. 2 3 4

GN Nuctesr Operating Comprny Unit I Cycle 26 Core Operating Limits Report utc26-0 Rev.0 Page 8 of l7 ry:r 6)fi '= o b$ ,'a Y 600 680 654 6.+0 -:80 ,550 Figure I Reactor Core Safefy Limits - Four Loops in Operation 60 80 Rated Thermal Porrer {Vo} U {:, 664.52 } t Unacceptable { f,, 65?.10 } 2,1-{0 PSIA { 96.638.5; ) 2250 PSIA \\ \\ \\ f:. 6r:.5+ ] ( 1(r2,62:.5:] \\ \\ \\ \\ \\ \\ \\ 1830 PSIA \\ L \\ \\ \\ I t_iu ourj ll ) \\ \\ { 130.5[F.08 ) { 111,587.3r) -l _i \\ \\ \\ I \\ Acceptable \\ { 1r0.563.sr ) -r40 30 40 IIJU t?0 140

aTn Nucf ear Operaling Company Unit 1 Cycle26 Core Operating Limits Report rI1C26-0 Rev.0 Page 9 of 17 UJT .0 5 7.0 6.0 1.0 Figure 2 Required Skutdswn Margin fcr tr{odes 3 & 4 300 1200 1600 RCS Critical Boron Concentraticn {ppm} $ar.{RI minur mosf reactir-e stuck rod) 4.0 3.0 q{l L z. ? ai 0 /.. 0 tAcceptable L

,{08
5. 15 0, 1.1{l Unacceptable 604. r.30 )

0.0 400 2000 2400

GT' Nucleir OperEling Company Unit 1 Cycle26 Core Operating Limits Report u1c26-0 Rev.0 Page 10 of l7 ryrr ) 7.CI 6.0 i.0 ,0 .0 4 .0 .0 Figure 3 Requi:ed Shutdown *ifargin for l{ode 5 800 1200 1600 RCS Critiral Boron Concentr*fior {ppnr) ffor ARI minus rnost reactive stuck rnd) c\\ bfi z 4. {J L J fi Acceptable

460 4 50 0 _ 1,30.1 Lrnacceptable 650,1.30 )

0.0 400 2000 t400

Uf Unit I Cycle 26 Core Operating Limits Report u1c26-0 Rev.0 Page 11 of17 Figure 4 MTC versus Power Level 6.0 7.0 5.0 -1.0 -2.0 .0 .0 .0 .0 0.0 4 J 2 tr o o q) (, c) () c) q) .0) F 0) t3a 40 50 60 70 Rated Thermal Power (%o) Unacceptable 5 5 \\ \\ \\ \\ Acceptable \\ \\ \\ \\ \\ \\ \\ \\ \\ \\ (100,0.0) -3.0 0 l0 20 30 80 90 100

G,lD Nuctesr Oprating Company UJT Unit 1 Cycle26 Core Operating Limits Report ulc26-0 Rev.0 Page 12 of 17 fignm S

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  • Control Bank A is already withdrawn to Full Out Position. Fully Withdrawn region shall be the condition where shutdown and control banks are at a position of either 259,254, or 256 steps withdrawn.

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  • GT' Nucledr OperEling Co$pany ufr Unit 1 Cycle26 Core Operating Limits Report ulc26-0 Rev 0

l3 of 17 120 110 100 90 80 \\Q u70 4) E60 tro 3 850 -50 -40 -30 Figure 6 AFD Limits versus Power Level -20 -10 0 t0 Axial Flux Difference (7o Delta-I) 40 20 30 l0 0 lt tt (-11,90) (11,e0) Unacceptable Unacceptable Acceptable (-31,50) (31,50) l l ll 20 30 40 50

G?tt Huclear Operuting Compary r:r Unit 1 Cycle26 Core Operating Limits Report u1c26-0 Rev.0 Page 14 of 17 Figure 7 K(Z) - Normalized FQ(Z) versus Core Height t.2 1.1 1.0 0.9 8 0. 4.7 0.6 0 0.4 .5 s V +r q) bT o N z 0.3 0.2 0.1 01 345 o/o Core Height (ft) 9 10 11 l2 1.3 14 ll lr I I, Core Elev. (ft) 0.0 7.0 14.0 FQ 2.55 2.5s 2.358 K(Z) 1.0 1.0 0.925 t I ,t ']T lr I 0.0 2

ry: Unit 1 Cycle 26 Core Operating Limits Report u1c26-0 Rev 0 15 of 17 Table 1 (Part I of 2) Unrodded Fxy for Each Core Height for Cycle Burnups Less Than 9,000 MWDMTU (Subject to the exclusion zones of COLR Section 2.7.4) Core Height (Ft.) Axial Point Unrodded Fxy Core Height (Ft.) Axial Point Unrodded Fxy 14.0 1 7.441 6.8 37 2.019 13.8 2 5.798 6.6 38 2.065 13.6 3 4.162 6.4 39 2.031 13.4 4 2.769 6.2 40 1.972 13.2 5 2.563 6.0 41 1.944 13.0 6 2.262 5.8 42 1.944 12.8 7 2.t62 5.6 43 1.943 12.6 8 2.152 5.4 44 1.935 t2.4 9 2.091 5.2 45 1.970 12.2 l0 2.026 5.0 46 2.04s 12.0 ll 1.986 4.8 47 2.069 I 1.8 l2 1.997 4.6 48 2.000 lt.6 13 2.043 4.4 49 1.949 tr.4 l4 2.027 4.2 50 1.955 tt.2 l5 1.970 4.0 51 1.955 11.0 l6 1.931 3.8 52 1.949 r0.8 t7 1.92r 3.6 53 1.964 10.6 18 1.91 I 3.4 54 2.022 10.4 t9 1.894 3.2 55 2.055 10.2 20 1.910 3.0 56 1.996 10.0 21 1.963 2.8 57 1.941 9.8 22 1.983 2.6 58 1.944 9.6 23 1.920 2.4 59 1.950 9.4 24 1.896 2.2 60 1.957 9.2 25 1.918 2.0 6l 1.994 9.0 26 1923 1.8 62 2.076 8.8 27 1.933 t.6 63 2.148 8.6 28 1.952 1.4 64 2.149 8.4 29 2.012 1.2 65 2.130 8.2 30 2.072 1.0 66 2.176 8.0 31 2.045 0.8 67 2.554 7.8 32 2.001 0.6 68 3.475 7.6 JJ 2.001 0.4 69 5.017 7.4 34 2.007 0.2 70 7.153 7.2 35 1.995 0.0 7l 10.681 7.0 36 1.979

GTIT Nuctrir Operating Cofi pany

r Unit 1 Cycle 26 Core Operating Limits Report utc26-0 Rev.0 Page 16 of l7 Table 1 (Part 2 of 2)

Unrodded Fxy for Each Core Height for Cycle Burnups Greater Than or Equal to 90000 MWD/MTU (Subject to the exclusion zones of COLR Section 2.7.4) Core Height (Ft.) AxialPoint Unrodded Fxy Core Height (Ft.) Axial Point Unrodded Fxy 14.0 1 6.574 6.8 37 2.204 13.8 2 5.253 6.6 38 2.247 13.6 J 3.927 6.4 39 2.209 13.4 4 2.797 6.2 40 2.142 13.2 5 2.637 6.0 41 2.106 13.0 6 2.342 5.8 42 2.099 t2.8 7 2.174 5.6 43 2.088 12.6 8 2.097 5.4 44 2.073 t2.4 9 2.029 5.2 45 2.093 12.2 10 1.998 5.0 46 2.134 t2.0 1l 1.991 4.8 47 2.132 I 1.8 12 2.019 4.6 48 2.070 I 1.6 13 2.084 4.4 49 2.021 tt.4 14 2.075 4.2 50 2.016 tl.2 15 2.020 4.0 5l 2.004 I 1.0 t6 1.975 3.8 52 1.988 10.8 17 1.999 3.6 53 1.990 10.6 l8 2.017 3.4 54 2.028 10.4 l9 2.020 3.2 55 2.056 10.2 20 2.054 3.0 56 1.978 10.0 2t 2.t21 2.8 57 1.908 9.8 22 2.r52 2.6 58 1.892 9.6 23 2.107 2.4 59 1.874 9.4 24 2.072 2.2 60 1.857 9.2 25 2.089 2.0 6l 1.865 9.0 26 2.102 1.8 62 1.905 8.8 27 2.107 1.6 63 1.931 8.6 28 2.12r t.4 64 1.903 8.4 29 2.173 1.2 65 1.918 8.2 30 2.226 1.0 66 2.028 8.0 31 2.t79 0.8 67 2.389 7.8 32 2.136 0.6 68 3.104 7.6 a-JJ 2.137 0.4 69 4.197 7.4 34 2.149 0.2 70 5.7 t0 7.2 35 2.157 0.0 7l 8.363 7.0 36 2.163

Unit I Cycle 26 Core Operating Limits Report utc26-0 Rev.0 Y: 17 of 17 Table 2 Core and Grid Plane Fry Exclusion Zones Axial Point Core Height (in.) Core Height (%) Top/Bottom Grid Axial Point Core Height (in.) Core Height (%) 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 J 163.2 97.1 Excluded 39 16.8 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 31.1 l0 146.4 87.1 46 60.0 35.7 Excluded ll 144.0 85.1 47 51.6 J+.J Excluded 12 141.6 84.3 48 55.2 32.9 Excluded l3 139.2 82.9 Excluded 49 s2.8 31.4 14 136.8 81.4 Excluded 50 s0.4 30.0 l5 134.4 80.0 Excluded 51 48.0 28.6 16 132.0 78.6 52 4s.6 27.1 17 129.6 '1',7.1 53 43.2 25.',7 18 127.2 '7 5.7 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 2l r20.0 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 11.1 24 112.8 61.1 60 26.4 15.1 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 3l 96.0 57.1 Excluded 67 9.6 5.7 Excluded 32 93.6 55.'7 68 7.2 Excluded 'r -) 91.2 54.3 69 4.8 2.9 Excluded Excluded 34 88.8 s2.9 70 2.4 1.4 Excluded Excluded 35 86.4 51.4 7t 0.0 0.0 Excluded Excluded 36 84.0 50.0}}

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