CPSES-200500835, (CPSES) Submittal of Unit 2, Cycle 9 Core Operating Limits Report

(CPSES) Submittal of Unit 2, Cycle 9 Core Operating Limits Report

ML051040434
Person / Time
Site:	Comanche Peak
Issue date:	04/07/2005
From:	Madden F TXU Power
To:	Document Control Desk, Office of Nuclear Reactor Regulation
References
CPSES-200500835, Tech. Spec. 5.6.5, TXX-05079
Download: ML051040434 (24)

Text

{{#Wiki_filter:. TXU Power TXU Power Mike Blevins Comanche Peak Steam Senior Vice President & Electric Station Chief Nuclear Officer P. O. Box 1002 (EO1) Glen Rose, TX 76043 Ref: Tech. Spec. 5.6.5 Tel: 254 897 5209 Fax 254 897 6652 mike.blevinsetxu.com CPSES-200500835 Log # TXX-05079 April 7, 2005 U. S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555

SUBJECT:

COMANCHE PEAK STEAM ELECTRIC STATION (CPSES) DOCKET NO. 50-446 SUBMITTAL OF UNIT 2, CYCLE 9 CORE OPERATING LIMITS REPORT Gentlemen: Enclosed is the Core Operating Limits Reports for CPSES Unit 2, Cycle 9. This report is prepared and submitted pursuant to Technical Specification 5.6.5. A*X01 A member of the STARS (Strategic Teaming and Resource Sharing) Alliance Callaway

• Comanche Peak
• Diablo Canyon
• Palo Verde
• South Texas Project
• Wolf Creek

TXX-05079 Page 2 of 2 This communication contains no new licensing basis commitments regarding CPSES Units I and 2. Sincerely, TXU Generation Company LP By: TXU Generation Management Company LLC, Its General Partner Mike Blevins By: X Fred W. Madden Director, Regulatory Affairs JDS/js Enclosure c - B. S. Mallett, Region IV M. C. Thadani, NRR Resident Inspectors, CPSES

ERX-05-001, Rev. 0 CPSES UNIT 2 CYCLE 9 CORE OPERATING LIMITS REPORT March 2005 Prepared: Daniel E. Brozak / A Date: 3/___/aS-Reactor Physics Reviewed: Date: _ _Z./___ onathan M. Ralston eactor Physics Reviewed: __ __ __ Date: ________ Hug6 DaSilva Safety Analysis Approved: a( i 1& 1 Date: 3______ Cohn T. Bosma Reac r Physics Supervisor Approved: _ Date: 3 -1 -?,oS Whee G. C e Safety An lysis Manager

DISCLAIMER The information contained in this report was prepared for the specific requirement of TXU Generation Company LP and may not be appropriate for use in situations other than those for which it was specifically prepared. TXU Generation Company LP PROVIDES NO WARRANTY HEREUNDER, EXPRESS OR IMPLIED, OR STATUTORY, OF ANY KIND OR NATURE WHATSOEVER, REGARDING THIS REPORT OR ITS USE, INCLUDING BUT NOT LIMITED TO ANY WARRANTIES ON MERCHANTABILITY OR FITNESS FOR A PARTICULAR PURPOSE. By making this report available, TXU Generation Company LP does not authorize its use by others, and any such use is forbidden except with the prior written approval of TXU Generation Company LP. Any such written approval shall itself be deemed to incorporate the disclaimers of liability and disclaimers of warranties provided herein. In no event shall TXU Generation Company LP have any liability for any incidental or consequential damages of any type in connection with the use, authorized or unauthorized, of this report or of the information in it. ii ERX-05-001, Rev. 0

COLR for CPSES Unit 2 Cycle 9 TABLE OF CONTENTS DISCLAIMER ...................................................... ii TABLE OF CONTENTS ............................................... iii LIST OF TABLES .................................................... iv LIST OF FIGURES .................................................. v SECTION PAGE 1.0 CORE OPERATING LIMITS REPORT .............................. 1 2.0 OPERATING LIMITS .......................................... 2 2.1 SAFETY LIMITS ........................................ 2 2.2 SHUTDOWN MARGIN ...................................... 2 2.3 MODERATOR TEMPERATURE COEFFICIENT .................... 2 2.4 ROD GROUP ALIGNMENT LIMITS ........................... 3 2.5 SHUTDOWN BANK INSERTION LIMITS ....................... 3 2.6 CONTROL BANK INSERTION LIMITS ........................ 4 2.7 PHYSICS TESTS EXCEPTIONS - MODE 2 .................... 4 2.8 HEAT FLUX HOT CHANNEL FACTOR ......................... 4 2.9 NUCLEAR ENTHALPY RISE HOT CHANNEL FACTOR ... .......... 5 2.10 AXIAL FLUX DIFFERENCE ................................ 6 2.11 REACTOR TRIP SYSTEM INSTRUMENTATION .................. 6 2.12 RCS PRESSURE, TEMPERATURE, AND FLOW DEPARTURE FROM NUCLEATE BOILING LIMITS .............................. 7 2.13 BORON CONCENTRATION .................................. 8

3.0 REFERENCES

    ......      .....................                                         8 iii                        ERX-05-001,       Rev. 0

COLR for CPSES Unit 2 Cycle 9 LIST OF TABLES TABLE PAGE 1 FE{Z) MARGIN DECREASES IN EXCESS OF 2 % PER 31 EFPD........ 9 iv ERX-05-001, Rev. 0

COLR for CPSES Unit 2 Cycle 9 LIST OF FIGURES FIGURE PAGE 1 REACTOR CORE SAFETY LIMITS .............................. 10 2 ROD BANK INSERTION LIMITS VERSUS THERMAL POWER ... .........11 3 K(Z) - NORMALIZED F,(Z) AS A FUNCTION OF CORE HEIGHT .12 4 W(Z) AS A FUNCTION OF CORE HEIGHT - (MAXIMUM) .13 5 W(Z) AS A FUNCTION OF CORE HEIGHT - (150 MWD/MTU) .14 6 W(Z) AS A FUNCTION OF CORE HEIGHT - (10,000 MWD/MTU) .15 7 W(Z) AS A FUNCTION OF CORE HEIGHT - (20,000 MWD/MTU) .16 8 AXIAL FLUX DIFFERENCE LIMITS AS A FUNCTION OF RATED THERMAL POWER .17 v ERX-05-001, Rev. 0

COLR for CPSES Unit 2 Cycle 9 1.0 CORE OPERATING LIMITS REPORT This Core Operating Limits Report (COLR) for CPSES UNIT 2 CYCLE 9 has been prepared in accordance with the requirements of Technical Specification 5.6.5. The Technical Specifications affected by this report are listed below: SL 2.1 SAFETY LIMITS LCO 3.1.1 SHUTDOWN MARGIN LCO 3.1.3 MODERATOR TEMPERATURE COEFFICIENT LCO 3.1.4 ROD GROUP ALIGNMENT LIMITS LCO 3.1.5 SHUTDOWN BANK INSERTION LIMITS LCO 3.1.6 CONTROL BANK INSERTION LIMITS LCO 3.1.8 PHYSICS TESTS EXCEPTIONS - MODE 2 LCO 3.2.1 HEAT FLUX HOT CHANNEL FACTOR LCO 3.2.2 NUCLEAR ENTHALPY RISE HOT CHANNEL FACTOR LCO 3.2.3 AXIAL FLUX DIFFERENCE LCO 3.3.1 REACTOR TRIP SYSTEM INSTRUMENTATION LCO 3.4.1 RCS PRESSURE, TEMPERATURE, AND FLOW DEPARTURE FROM NUCLEATE BOILING LIMITS LCO 3.9.1 BORON CONCENTRATION 1 ERX-05-001, Rev. 0

COLR for CPSES Unit 2 Cycle 9 2.0 OPERATING LIMITS The cycle-specific parameter limits for the specifications listed in Section 1.0 are presented in the following subsections. These limits have been developed using the NRC-approved methodologies specified in Technical Specification 5.6.5b, Items 5 and 9 through 19, as supplemented by Items 20 and 21 (as of Amendment 113). These limits have been determined such that all applicable limits of the safety analysis are met. 2.1 SAFETY LIMITS (SL 2.1) 2.1.1 In MODES 1 and 2, the combination of thermal power, reactor coolant system highest loop average temperature, and pressurizer pressure shall not exceed the safety limits specified in Figure 1. 2.2 SHUTDOWN MARGIN (SDM) (LCO 3.1.1) 2.2.1 The SDM shall be greater than or equal to 1.3% Ak/k in MODE 2 with K.,, < 1.0, and in MODES 3, 4, and 5. 2.3 MODERATOR TEMPERATURE COEFFICIENT (MTC) (LCO 3.1.3) 2.3.1 The MTC upper and lower limits, respectively, are: The BOL/ARO/HZP-MTC shall be less positive than +5 pcm/ F. The EOL/ARO/RTP-MTC shall be less negative than -40 pcm/ F. 2 ERX-05-001, Rev. 0

COLR for CPSES Unit 2 Cycle 9 2.3.2 SR 3.1.3.2 The MTC surveillance limit is: The 300 ppm/ARO/RTP-MTC shall be less negative than or equal to -31 pcm/ F. The 60 ppm/ARO/RTP-MTC shall be less negative than or equal to -38 pcm/ F. where: BOL stands for Beginning of Cycle Life ARO stands for All Rods Out HZP stands for Hot Zero THERMAL POWER EOL stands for End of Cycle Life RTP stands for RATED THERMAL POWER 2.4 ROD GROUP ALIGNMENT LIMITS (LCO 3.1.4) 2.4.1 The SDM shall be greater than or equal to 1.3% Ak/k in MODES 1 and 2. 2.5 SHUTDOWN BANK INSERTION LIMITS (LCO 3.1.5) 2.5.1 The shutdown rods shall be fully withdrawn. Fully withdrawn shall be the condition where shutdown rods are at a position within the interval of 218 and 231 steps withdrawn, inclusive. 3 ERX-05-001, Rev. 0

COLR for CPSES Unit 2 Cycle 9 2.6 CONTROL BANK INSERTION LIMITS (LCO 3.1.6) 2.6.1 The control banks shall be limited in physical insertion as shown in Figure 2. 2.6.2 The control banks shall always be withdrawn and inserted in the prescribed sequence. For withdrawal, the sequence is control bank A, control bank B, control bank C, and control bank D. The insertion sequence is the reverse of the withdrawal sequence. 2.6.3 A 115 step Tip-to-Tip relationship between each sequential control bank shall be maintained. 2.7 PHYSICS TESTS EXCEPTIONS - MODE 2 (LCO 3.1.8) 2.7.1 The SDM shall be greater than or equal to 1.3% Ak/k in MODE 2 during PHYSICS TESTS. 2.8 HEAT FLUX HOT CHANNEL FACTOR (F(Z)) (LCO 3.2.1) F0 2.8.1 F0 (Z) [K(Z)] for P > 0.5 p FFRTP Q F0 (Z) S EK(Z)] for P S 0.5

0.5 where

P = T'HERMAL POWER RATE:D THERMAL POWER 4 ERX-05-001, Rev. 0

COLR for CPSES Unit 2 Cycle 9 NT, 2.8.2 Fo = 2.42 2.8.3 K(Z) is provided in Figure 3. 2.8.4 Maximum elevation dependent W(Z) values are given in Figure 4. Figures 5, 6, and 7 give burnup dependent values for W(Z). Figures 5, 6, and 7 can be used in place of Figure 4 to interpolate or extrapolate (via a three point fit) the W(Z) at a particular burnup. 2.8.5 SR 3.2.1.2 If the two most recent F,(Z) evaluations show an increase in the expression maximum over Z C Fc(Z) / K(Z) ], the burnup dependent values in Table 1 shall be used instead of a constant 2% to increase F."(Z) per Surveillance Requirement 3.2.1.2.a. A constant factor of 2% shall be used for all cycle burnups that are outside the range of Table 1. 2.9 NUCLEAR ENTHALPY RISE HOT CHANNEL FACTOR (FNAHI (LCO 3.2.2) 2.9.1 FNAH C F T1AH [1 + PFAH (1-P)J where: P = THERMAL POWER RATED THERMAL POWER 2.9.2 F'"&H = 1.55 2.9.3 PFAH = 0.3 5 ERX-05-001, Rev. 0

COLR for CPSES Unit 2 Cycle 9 2.10 AXIAL FLUX DIFFERENCE (AFD) (LCO 3.2.3) 2.10.1 The AFD target band is +5%, -12% at 100% RTP linearly expanding to +20%, -17% at 50% RTP. Below 50% RTP, the AFD target band remains constant at +20%, -17%. 2.10.2 The AFD Acceptable Operation Limits are provided in Figure 8. 2.11 REACTOR TRIP SYSTEM (RTS) INSTRUMENTATION (LCO 3.3.1) 2.11.1 The numerical values pertaining to the Overtemperature N-16 reactor trip setpoint are listed below; R. = 1.13 KR = 0.0145 /'F KR = 0.00075 /psig T, = 560.5 'F P1 2 2235 psig T, > 10 sec T, < 3 sec f 1 (Aq) = 0.00 ((q,-q.) + 65%) when (q,-qb) < -65% RTP

                     = 0%   when -65% RTP <     (q,-q%) < +7.0% RTP
                     = 2.27 -{(q,-qb)   -  7.0%)    when (q,-q 1 ) > +7.0% RTP 6                         ERX-05-001,  Rev. 0

COLR for CPSES Unit 2 Cycle 9 2.12 RCS PRESSURE, TEMPERATURE, AND FLOW DEPARTURE FROM NUCLEATE BOILING (DNB) LIMITS (LCO 3.4.1) 2.12.1 RCS DNB parameters for pressurizer pressure, RCS average temperature, and RCS total flow rate shall be within the surveillance limits specified below: 2.12.2 SR 3.4.1.1 Pressurizer pressure > 2220 psig (4 channels)

                                   >  2222 psig (3 channels)

The pressurizer pressure limits correspond to the analytical limit of 2205 psig used in the safety analysis with allowance for measurement uncertainty. These uncertainties are based on the use of control board indications and the number of available channels. 2.12.3 SR 3.4.1.2 RCS average temperature < 592 'F (4 channels) 5 592 F (3 channels) The RCS average temperature limits correspond to the analytical limit of 595.7 'F used in the safety analysis with allowance for measurement uncertainty. These uncertainties are based on the use of control board indications and the number of available channels. 7 ERX-05-001, Rev. 0

COLR for CPSES Unit 2 Cycle 9 2.12.4 SR 3.4.1.3 The RCS total flow rate based on precision heat balance shall be 2 408,000 gpm 2.12.5 SR 3.4.1.4 The RCS total flow rate based on precision heat balance shall be > 408,000 gpm The required RCS flow, based on an elbow tap differential pressure instrument measurement prior to MODE 1 after the refueling outage, shall be greater than 317,000 gpm. 2.13 BORON CONCENTRATION (LCO 3.9.1) 2.13.1 The required refueling boron concentration is 2038 ppm.

3.0 REFERENCES

Technical Specification 5.6.5. 8 ERX-05-001, Rev. 0

COLR for CPSES Unit 2 Cycle 9 Table 1 F,(Z) MARGIN DECREASES IN EXCESS OF 2 % PER 31 EFPD Cycle Maximum Decrease Burnup In F. (Z) Margin (MWD/MTU) (Percent) 6400 2.00 6610 2.12 6820 2.12 7030 2.12 7240 2.18 7450 2.20 7660 2.22 7860 2.27 8070 2.19 8280 2.13 8490 2.06 8700 2.00 Note: All Cycle burnups outside the range of the table shall use a constant 2% decrease in F,(Z) margin for compliance with the 3.2.1.2.a Surveillance Requirements. Linear interpolation is acceptable to determine the F (Z) margin decrease for cycle burnups which fall between the specified burnups. 9 ERX-05-001, Rev. 0

COLR for CPSES Unit 2 Cycle 9 FIGURE 1 REACTOR CORE SAFETY LIMITS od_24-2445 psg n_ Unacceptable Operation JJ 620 V 4 6I 590 Opeaton. 610 _ _ _ 60.2004.6008.10.11. 600 Acceptable Operation 590 580 - _ _ _ _ _ _ _ _ _ _ _ 1__ _ _ _ _ 1__ _ _ _ _ _ _ _ _ _ _ _ 0.0 20.0 40.0 60.0 80.0 1.00. 0 116.4 Percent of Rated Thermal Power 10 ERX-05-001, Rev. 0

COLR for CPSES Unit 2 Cycle 9 FIGURE 2 ROD BANK INSERTION LIMITS VERSUS THERMAL POWER 240 * -.---E-,---.- - - I - III t4I (25.3,218) I I - I II I I I Azf.jt (79.6,218)- 200 1. , , ...,, I WI1I1 W=-+It BANK B t80 1 2t, A 160 J 4 -1 (100,146) _TT_ a, 140 J C 0 120 Il l - Il l l i l t 7TT' to 100 _mT -44 0 5 80 H4 BANK 1) JJ 0 go 60 0,49)- IL 40 20 L I (31.0 n v 0 10 20 30 40 50 60 70 80 90 100 PERCENT OF RATED THERMAL POWER NOTES: 1. Fully withdrawn shall be the condition where control rods are at a position within the interval of 218 and 231 steps withdrawn, inclusive.

2. Control Bank A shall be fully withdrawn.

11 ERX-05-001, Rev. 0

COLR for CPSES Unit 2 Cycle 9 FIGURE 3 K(Z) - NORMALIZED FQ(Z) AS A FUNCTION OF CORE HEIGHT 1.1

            -1 111111 I (0.011.0) 111111 it I I I I 11 tfltl- JH_ IIIIiIII                (6.011.0)

I 111111 I flIf I.-Hill 1.0 _111- flfl-l III I I iII., I I] I I I 0.9 ii 0.6 .11- 1 1-

                                                           ....      -     I'...-                                 -                  -         -       ..             ...

i -1I . . . . . . .1-4-4--H+I~ 4-I--4-I-- I4--+---4---I-4I-4----4.-.- 4--+- - -4+ -I4+t------I-0.7 . I . . . . . . . . . . . . . . . . I . i I . . I . I . I I . . . . N 0.6 I 4--4.4.iJ1----.-4---- I- 4-f t-1---4-4-4-I -.- 4-4-f- I4------

                                                                                                       ....           . 4.. .         . . .4I--4-4-.
                                                                                                                                           ..   . ..        .                 I . . . .- I 0

0.5 . I . . . . . . . . . .I I . I . . . . I . I . I . I . - . . I . . . . N4 0.4 . . . . . . . . . I . . . . . . 0.3 0.2 I :'I II II'I .I I I I I.Il  : 0.1 I..I I I . I . .. l i .  ! l:. . l i l 0.0 . I . . . I . . . I I . . . . . . - . - - 0 1 2 3 4 5 6 7 8 9 10 11 12 BOTTOM CORE HEIGHT (FEET) TOP Axial Axial Axial Axial Node K(Z) Node K (Z) Node K (Z) Node K(Z) 61 0.9250 53 0.9450 45 0. 9650 37 0.9850 60 0.9275 52 0.9475 44 0. 9675 36 0.9875 59 0.9300 51 0.9500 43 0. 9700 35 0. 9900 58 0.9325 50 0.9525 42 0.9725 34 0.9925 57 0.9350 49 0.9550 41 0.9750 33 0.9950 56 0.9375 48 0.9575 40 0. 9775 32 0.9975 55 0.9400 47 0.9600 39 0.9800 1 - 31 1.0000 54 0.9425 46 0.9625 38 0. 9825 Core Height (ft) = (Node - 1)

• 0.2 12 ERX-05-001, Rev. 0

COLR for CPSES Unit 2 Cycle 9 FIGURE 4 W(Z) AS A FUNCTION OF CORE HEIGHT (MAXIMUM) 1.300 - r 1.250 1.200 9 Ii 1.150

           ----          K-H                          -

1.100 1.050 1.000 ti-zz=z 7 -z - 0 1 2 3 4 5 6 7 8 9 10 11 12 BOTTOM CORE HEIGHT (FEET) TOP Axial Axial Axial Axial Node W(Z) Node W (Z) Node W(Z) Node W (Z) 52 - 61 41 1.137 30 1.118 19 1.146 51 1.129 40 1.135 29 1.125 18 1.149 50 1.133 39 1.134 28 1.131 17 1.153 49 1.134 38 1.131 27 1.136 16 1.158 48 1.131 37 1.128 26 1.141 15 1.171 47 1.128 36 1.125 25 1.144 14 1.183 46 1.130 35 1.120 24 1.147 13 1.194 45 1.132 34 1.112 23 1.148 12 1.203 44 1.135 33 1.107 22 1.149 11 1.213 43 1.136 32 1.108 21 1.149 1 - 10 _ _ 42 1.137 31 1.110 20 1.148 Core Height (ft) = (Node - 1)

• 0.2 13 ERX-05-001, Rev. 0

COLR for CPSES Unit 2 Cycle 9 FIGURE 5 W(Z) AS A FUNCTION OF CORE HEIGHT (150 MWD/MTU) 1.300 iii. ii _ - - -. _ ___ 1.250 1.200

          *4*V----                                 Hv                                -

D 1.150 1.100 __ _ - ui 1.050

                                              -                                 II 1.000 0        1     2       3          4      5      6        7        8       9      10     11       12 BOTTOM                             CORE HEIGHT (FEET)                                          TOP Axial                     Axial                         Axial                      Axial Node        W(Z)          Node        W(Z)             Node        W (Z)          Node      W (Z) 52 - 61                         41      1.121             30        1.111             19     1.146 51        1.113              40      1.124             29        1.114             18     1.149 50        1.104              39      1.122             28        1.117             17     1.153 49        1.100              38      1.116             27        1.121             16     1.158 48        1.103              37      1.110             26        1.124             15     1.163 47        1.107             36       1.107             25        1.127             14     1.167 46        1.111             35       1.106             24        1.131             13     1.171 45        1.113             34       1.106             23        1.134             12     1.175 44        1.114             33       1.107             22        1.138            11      1.177 43        1.114             32       1.108             21        1.141          1 - 10        _ _

42 1.117 31 1.110 20 1.143 Core Height (ft) = (Node - 1)

• 0.2 14 ERX-05-001, Rev. 0

COLR for CPSES Unit 2 Cycle 9 FIGURE 6 W(Z) AS A FUNCTION OF CORE HEIGHT (10,000 MWD/MTU) 1.300 1.250 1.200 P ' 3: 2 1.150 X 1.100 1.050 1.000 0 1 2 3 4 5 6 7 8 9 10 11 12 BOTTOM CORE HEIGHT (FEET) TOP Axial Axial Axial Axial Node W (Z) Node W(Z) Node W (Z) Node W(Z) 52 - 61 41 1.126 30 1.109 19 1.140 51 1.129 40 1.124 29 1.112 18 1.143 50 1.133 39 1.121 28 1.116 17 1.148 49 1.134 38 1.119 27 1.120 16 1.155 48 1.131 37 1.115 26 1.124 15 1.162 47 1.128 36 1.109 25 1.128 14 1.169 46 1.127 35 1.105 24 1.132 13 1.175 45 1.127 34 1.103 23 1.135 12 1.180 44 1.128 33 1.104 22 1.136 11 1.184 43 1.128 32 1.105 21 1.137 1 - 10 42 1.128 31 1.107 20 1.138 Core Height (ft) = (Node - 1)

• 0.2 is ERX-05-001, Rev. 0

COLR for CPSES Unit 2 Cycle 9 FIGURE 7 W(Z) AS A FUNCTION OF CORE HEIGHT (20,000 MWDIMTU) 1.300 1.250 - - =.=.zzzzi. -

                                     -        -3/4-1.200 D3 1.150 1.100 1.050 1

1.000 0 1 2 3 4 5 6 7 8 9 10 11 12 BOTTOM CORE HEIGHT (FEET) TOP Axial Axial Axial Axial Node W(Z) Node W (Z) Node W(Z) Node w(Z) 52 - 61 41 1.137 30 1.118 19 1.145 51 1.121 40 1.135 29 1.125 18 1.143 50 1.123 39 1.134 28 1.131 17 1.147 49 1.125 38 1.131 27 1.136 16 1.157 48 1.127 37 1.128 26 1.141 15 1.171 47 1.128 36 1.125 25 1.144 14 1.183 46 1.130 35 1.120 24 1.147 13 1.194 45 1.132 34 1.112 23 1.148 12 1.203 44 1.135 33 1.106 22 1.149 11 1.213 1.149 _ _ 43 1.136 32 1.104 21 1 - 10 42 1.137 31 1.110 20 1.148 Core Height (ft) = (Node - 1)

• 0.2 16 ERX-05-001, Rev. 0

COLR for CPSES Unit 2 Cycle 9 FIGURE 8 AXIAL FLUX DIFFERENCE LIMITS AS A FUNCTION OF RATED THERMAL POWER 100 (-152 0) 90 UNACCEPTABLE _ _ _+/- UNACCEPTABLE - OPERATION _ _j _ f OPERATION 90

              -            -                ACCEPTABLE OPERATION___

70 0 60 W cz: Oa 50 0 W PH C.) 40 IAL XWX X~~ 44+4X4 w 30 WX w[-A A-I 20 10

                           -= Ti                    fX X+     -TT:= 4FLIL-XT1 T       -a+ I 0
        -40     -30      -20        -10           0        10      20        30          40 DEVIATION FROM TARGET AXIAL FLUX DIFFERENCE (%)

17 ERX-05-001, Rev. 0}}