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Category:FUEL CYCLE RELOAD REPORTS
MONTHYEARML20217H3631999-10-14014 October 1999 Rev 0 to COLR for North Anna 2 Cycle 14 Pattern Su ML20210Q9931999-07-31031 July 1999 Rev 1 to COLR for North Anna Power Station,Unit 2 Cycle 13 Pattern Ud ML20154L0691998-10-14014 October 1998 COLR for North Anna Power Station Unit 1 Cycle 14 Pattern Xy ML20216A8971998-05-0606 May 1998 Rev 0 to Cycle 13 Pattern Ud COLR for North Anna Unit 2 ML20148J8351997-05-31031 May 1997 COLR North Anna Unit 1 Cycle 13 Pattern Og ML20129F8591996-10-21021 October 1996 COLR North Anna 2 Cycle 12 Pattern Cv, Rev 0 ML20112E2341996-04-30030 April 1996 Rev 0 to NE-1068, North Anna Unit 1,Cycle 11 Core Performance Rept, for Apr 1996 ML20107D2231996-02-29029 February 1996 COLR North Anna 1 Cycle 12 Pattern Bl, Rev 0 ML20107K1141995-05-31031 May 1995 Rev 0 of COLR North Anna 2 Cycle 11 Pattern Um ML20084G9211995-05-12012 May 1995 Rev 0 to NE-1024, North Anna Unit 2,Cycle 10 Core Performance Rept, Dtd May 1995 ML20078P9611994-11-30030 November 1994 Cycle 10 Core Performance Rept ML20076J1461994-09-30030 September 1994 Rev 0 to COLR North Anna Cycle 11 Pattern Bw ML18153B3851993-11-30030 November 1993 Reload Nuclear Design Methodology. ML20058F1311993-11-0505 November 1993 Rev 0 to North Anna Unit 2,Cycle 9 Core Performance Rept ML20059G8951993-10-31031 October 1993 COLR for North Anna 2 Cycle 10 Pattern Re, Rev 1 ML20101U1881992-06-24024 June 1992 Rev 0 to NE-895, North Anna Unit 2,Cycle 9 Startup Physics Tests Rept ML20101J5871992-05-31031 May 1992 Rev 0 to Technical Rept NE-876, North Anna Unit 2,Cycle 8 Core Performance Rept ML20096C6161992-04-30030 April 1992 Rev 0 to North Anna 2,Cycle 9 Loading Pattern ET Core Operating Limits Rept ML20094K3351992-02-29029 February 1992 Core Operating Limits Rept ML20077E4111991-05-31031 May 1991 Rev 0 to Technical Rept NE-838, North Anna Unit1,Cycle 8 Core Performance Rept ML20066F9541991-01-18018 January 1991 1,Cycle 9,Pattern R8 Core Surveillance Rept ML20028H8601991-01-16016 January 1991 Rev 0 to NE-817, North Anna Unit 2,Cycle 8 Startup Physics Test Rept. W/910128 Ltr ML20028H8621991-01-0909 January 1991 Rev 0 to NE-799, North Anna Unit 2,Cycle 7 Core Performance Rept. W/910128 Ltr ML20058F3841990-10-30030 October 1990 Revised Proposed Changes to Core Operating Limits Repts ML20058C1661990-10-25025 October 1990 Core Surveillance Rept for North Anna 2 Cycle 8 Pattern Qf ML20064A8731990-09-11011 September 1990 Cycle 8 Core Surveillance Rept ML20043G1921990-06-0808 June 1990 Core Surveillance Rept for North Anna 2,Cycle 7 W/Extended License Burnup Limit. ML20012E8311990-03-26026 March 1990 Cycle 8 Core Operating Limits Rept. ML20012E8321990-03-26026 March 1990 Cycle 7 Core Operating Limits Rept. ML20247H0291989-08-31031 August 1989 Cycle 7 Core Performance Rept ML20245C4931989-06-0505 June 1989 Cycle 8 Relaxed Power Distribution Control Pattern - Core Surveillance Rept ML20245L0931989-04-30030 April 1989 Rev 0 to North Anna Unit 2 Cycle 6 Core Performance Rept ML18149A4301986-09-30030 September 1986 Rev 1-A to Reload Nuclear Design Methodology. ML20155K6461986-05-22022 May 1986 Rev 1 to North Anna Unit 2,Cycle 5,Relaxed Power Distribution Control Core Surveillance Rept for FQ=2.20 ML20155F5721986-03-31031 March 1986 Cycle 4 Core Performance Rept ML20151N5671985-11-30030 November 1985 Cycle 5 Core Performance Rept ML20135H9491985-08-31031 August 1985 Rev 1 to Reload Nuclear Design Methodology ML20069K3671983-04-30030 April 1983 Cycle 2 Core Performance Rept 1999-07-31
[Table view] Category:TEXT-SAFETY REPORT
MONTHYEARML20217N9281999-10-20020 October 1999 Special Rept:On 991003,PZR PORV Actuation Mitigated RCS low- Temp Overpressure Transient.Caused by a RCP Facilitating Sweeping of Entrained Air Out of RCS Loops.Operating Procedure 2-OP-5.1 Will Be Revised ML20217H3631999-10-14014 October 1999 Rev 0 to COLR for North Anna 2 Cycle 14 Pattern Su ML18152A2811999-10-12012 October 1999 Technical Basis for Elimination of Nozzle Inner Radius Insps (for Nozzles Other than Reactor Vessel),Technical Basis for ASME Section XI Code Case N-619. ML20212J9251999-10-0101 October 1999 Safety Evaluation Accepting Licensee Relief Request IWE-3 for Second 10-year ISI for Plant ML20217D6851999-09-30030 September 1999 Monthly Operating Repts for Sept 1999 for North Anna Power Station,Units 1 & 2.With ML20211N2611999-09-0808 September 1999 Safety Evaluation Concluding That Proposed Irradiation of Fuel Rods Beyond Current Lead Rod Burnup Limit & Clarification of Terminology with Respect to Reconstituted Fuel Assemblies Acceptable ML20211J2561999-08-31031 August 1999 Safety Evaluation Accepting Elimination of Augmented ISI Program for Pressurizer Spray Lines at North Anna Unit 2 ML20216E5011999-08-31031 August 1999 Monthly Operating Repts for Aug 1999 for Naps,Units 1 & 2. with ML20211J2421999-08-31031 August 1999 Safety Evaluation Supporting Removal of Augmented Insp Program on RCS Bypass Lines from Licensing Basis of North Anna,Units 1 & 2 ML20210T0791999-08-13013 August 1999 Safety Evaluation Concluding That Revised Withdrawal Schedules for North Anna Units 1 & 2 Satisfy Requirements of App H to 10CFR50 & Therefore Acceptable ML20210S1411999-07-31031 July 1999 Monthly Operating Repts for July 1999 for North Anna Power Station.With ML20210Q9931999-07-31031 July 1999 Rev 1 to COLR for North Anna Power Station,Unit 2 Cycle 13 Pattern Ud ML20209E5641999-06-30030 June 1999 Monthly Operating Repts for June 1999 for North Anna Power Stations,Units 1 & 2.With ML20195G1901999-05-31031 May 1999 Monthly Operating Rept for May 1999 for NAPS Units 1 & 2. with ML20206L4831999-05-10010 May 1999 SER Accepting Request to Delay Submitting Plant,Unit 1 Class 1 Piping ISI Program for Third Insp Interval Until 010430, to Permit Development of Risk Informed ISI Program for Class 1 Piping ML20206Q6671999-04-30030 April 1999 Monthly Operating Repts for Apr 1999 for North Anna Power Station,Units 1 & 2.With ML20205S0391999-04-21021 April 1999 SER Accepting Request for Relief IWE5,per 10CFR50.55a(a)(3) & Proposed Alternatives for IWE2,IWE4,IWE6 & IWL2 Authorized Per 10CFR50.55a(a)(3)(ii) ML20205K3041999-03-31031 March 1999 Monthly Operating Repts for Mar 1999 for North Anna Power Station,Units 1 & 2.With ML20207K5921999-02-28028 February 1999 Monthly Operating Repts for Feb 1999 for North Anna Power Station,Units 1 & 2.With ML20207E1731999-02-18018 February 1999 Informs Commission of Status of Preparations of IAEA Osart Mission to North Anna Nuclear Power Plant Early Next Year ML20205A0241998-12-31031 December 1998 Summary of Facility Changes,Tests & Experiments,Including Summary of SEs Implemented at Plant During 1998,per 10CFR50.59(b)(2).With ML20199C8781998-12-31031 December 1998 Monthly Operating Repts for Dec 1998 for North Anna Power Station,Units 1 & 2.With ML20198H9541998-12-0303 December 1998 Safety Evaluation Authorizing Proposed Alternative for Remainder of Second 10-yr Insp Interval for Plant ML20198J5561998-12-0303 December 1998 ISI Summary Rept for North Anna Power Station,Unit 1 1998 Refueling Outage Owner Rept for Inservice Insps ML20197G8551998-11-30030 November 1998 Monthly Operating Repts for Nov 1998 for North Anna Power Station,Units 1 & 2.With ML20196G1381998-11-0303 November 1998 Safety Evaluation Authorizing Rev to Relief Request NDE-32 for Remainder of Second 10-yr Insp Interval for Each Unit ML20195D0571998-10-31031 October 1998 Monthly Operating Repts for Oct 1998 for North Anna Power Station,Units 1 & 2.With ML20154L0691998-10-14014 October 1998 COLR for North Anna Power Station Unit 1 Cycle 14 Pattern Xy ML20155J6911998-10-0909 October 1998 Staff Response to Tasking Memorandum & Stakeholder Concerns ML20154H4001998-09-30030 September 1998 Monthly Operating Repts for Sept 1998 for North Anna Power Station,Units 1 & 2.With ML20151X8011998-09-10010 September 1998 Special Rept:On 980622,groundwater Level at Piezometer P-22 Was Again Noted to Be Above Max Water Level by 0.71 Feet. Increased Frequency of Piezometer Monitoring & Installed Addl Piezometers at Toe of Slope Along Southwest Section ML20151W4711998-08-31031 August 1998 Monthly Operating Repts for Aug 1998 for North Anna Power Station Units 1 & 2.With ML20237A4341998-07-31031 July 1998 Monthly Operating Repts for July 1998 for North Anna Power Station,Units 1 & 2 ML20236V1251998-07-14014 July 1998 ISI Summary Rept for Naps,Unit 2,1998 Refueling Outage Owners Rept of Isis ML20236K5531998-07-0707 July 1998 SER Accepting Request for Change in ISI Commitment on Protection Against Pipe Breaks Outside Containment ML20236M3381998-06-30030 June 1998 Monthly Operating Repts for June 1998 for North Anna Power Station,Units 1 & 2 ML20248M1011998-05-31031 May 1998 Monthly Operating Repts for May 1998 for North Anna Power Station,Units 1 & 2 ML20248C8831998-05-29029 May 1998 SER Accepting Alternatives Proposed by Licensee for Use of Code Case N-535,pursuant to 10CFRa(a)(3)(i) in ASME Section XI Inservice Insp Program ML20247K9281998-05-15015 May 1998 Special Rept:On 980428,letdown PCV Exhibited Slow Response When C RCP Was Started.Cause to Be Determined.Review of Operating Procedure Will Be Performed to Determine If Enhancements Are Necessary ML20216A8971998-05-0606 May 1998 Rev 0 to Cycle 13 Pattern Ud COLR for North Anna Unit 2 ML20247F4441998-04-30030 April 1998 Monthly Operating Repts for Apr 1998 for North Anna Power Station,Units 1 & 2 ML20217B5321998-04-20020 April 1998 Safety Evaluation Supporting Proposed Alternative to ASME Code for Surface Exam of Seal Welds on Threaded Caps for Plant Reactor Vessel Head Penetrations for part-length CRDMs ML20217H9611998-04-0707 April 1998 Special Rept:On 980216,groundwater Level at Piezometer P-22, Again Noted to Be Above Max Water Level by 0.41 Feet.Design Package for Installation of Addl Standpipe Piezometers at Toe of Slope Southeast Section,Developed ML20216B1891998-03-31031 March 1998 Monthly Operating Repts for Mar 1998 for North Anna Power Station,Units 1 & 2 ML20216E8801998-03-0606 March 1998 Safety Evaluation Authorizing Licensee Request for Relief from ASME Code Requirements,Paragraph IWA-2400(c) (Summer Edition W/Summer 1983 Addenda),For Upcoming Naps,Unit 1 Outage,Per 10CFR50.55a(a)(3)(ii) ML20216E2561998-02-28028 February 1998 Monthly Operating Repts for Feb 1998 for North Anna Power Station,Units 1 & 2 ML20199J6431998-02-0202 February 1998 Safety Evaluation Approving Request for Approval to Repair Flaws in Accordance W/Gl 90-05 for ASME Code Class 3 SW Piping for North Anna,Unit 1,as Submitted in ISI Relief Request NDE-46 on 971218 ML20202D5811998-01-31031 January 1998 Monthly Operating Repts for Jan 1998 for North Anna Power Station,Units 1 & 2 ML20198S7571998-01-15015 January 1998 Safety Evaluation Accepting Licensee Request for Approval to Repair Flaws IAW GL-90-05 for ASME Code Class 3 Svc Water Piping ML20198P1351997-12-31031 December 1997 Monthly Operating Repts for Dec 1997 for North Anna Power Station,Units 1 & 2 1999-09-08
[Table view] |
Text
7 NORTH ANNA 1 CYCLE 8 RPDC PATTERN AN CORE SURVEILLANCE R 1
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6906260207 690626 PDR ADOOK 050003:.t F' PDC 1
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NORTH ANNA UNIT 1 CYCLE 8 CORE SURVEILLANCE REPORT
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This Core Surveillance Report is provided in accordance with Section 6.9.1.7 of the North Anna Unit.1 Technical Specifications. 3 1
1 The burnup-dependent' Cycle 8 N(z) function- for Technical Specification !
4.2.2.2.C is shown in Figures 1-6. N(z)'was calculated according to the '
procedure of VEP-NE-1-A. j I
.)
The N(z) function
- will be used to confirm that the heat flux hot channel .i factor, FQ(z), will be limited to the Technical Specifications values of 1 J
2.19 K(z)
FQ(z) s ---------- , P > 0.5 and P
1 FQ(z) s 4.38 K(Z), P s 0.5. !
- The Cycle 8 Axial Flux Difference (AFD) limits for Tc:hnical Specification 3.2.1 are shown in. Figure 7. These limits were calculated according to i the methods.of VEP-NE-1-A and are comparable to the Cycle 7 limits.
j i
The limits on Axial Flux Difference assure that the FQ(z) upper bound envelope is not exceeded during either normal operation or in the event of xenon redistribution following power changes.
- The N(z) function, when applied to a power distribution measured under equilibrium conditions, demonstrates that the initial conditions assumed.
in the LOCA analysis are met, ilong with.the ECCS acceptance criteria of 10CFR50.46. .
P i
FIGURE 1 - N(Z) FUNCTION FOR NIC8 AT 2893 MW l FROM 0 to 1000 MWD /MTU BURNUP i
. TOP A 2 BOTTOM 15 PERCENT EXCLUDED AS PER' TECH SPEC 4.4.2.z.G HEIGHT N(Z) j (FEET) 1.80 1 253 ,
2.00 1.245 j 2.20 1.236 ;
2.40. 1.226 l 2.60 1.216 I 2.80 1.204 l 1.26+00 3.00. 1.192 1
-3.20 1.180
\ 3.40 1.167
( 3.60 1.157-3.80 '1.148 4.00 1.143.
1.22+00 4.20 1.139 i me 4.40 1.136 4 5 4.60 1.131.
d 4.80 1.124
- 5.00
$ 1.117 d
" 5.20. 1.109 E . 18+00 ( 5.40 5.60 1.104 1.101
"' 5.80 1.104 6.00 1.107 d 6.20 1.112 8 / 6.40 1.114 W fN / 6.60 1.120 g 1.14+00 ' / \ / 6.80 1.127
/ 7.00 1.134
/ 7.20 7.40 7.60 1.139 1.143 1.147 1.10 M 0. ,
\N/ 7.80 8.00 1.150 1.151 8.20 1.151 0.00+D0 2. 00 + Of* 4.00+00 8.00+00 8.00+00 1.00+01 8.40 1:149 COREHEIGHT(FEET) 8.60 1.147 8.80 1.142
. 9.00 1.134 9.20 1.129 9.40 1.131 9.60 1.139 9.80 '
1.145 10.00 1.151 10.20 1.157
FIGlRE 2 - N(Z) FUNCTION FOR NIC8 AT 2893'MW FROM 1000 to 3000 MWD /MTU BLRNUP TOP AND BOTTOM 15 PERCENT EXCLUDED AS PER TECH SPEC 4.2.2.2.G HEIGHT. N(Z)'
(FEET).
1.80 1.253 2.00' 1.245 2.20 1.236s 2.40 1.226 2.60 1.216 2.80 '1.204 3.00 1.192
-1.26+00 3.20 1.180 3.40 1.167.
\ 3.60 :1.157
' 3.80 1.148 4.00- ~ 1.143 ~
-4.20 1.139 4 an 1.135 1.22+00 4.60 1.130 h'
a 4.80- 1.122 i /
A 5.00 1.116
\ 5.20 1.118 C )
E' j
/ / 5.40 1.130
( / 5.60 1.141
= 1.18+00 \ / \/ 5.80 1.154 E v 6.00 f 1.164 E
3 ;
[ 6.20 6.40 1.172 1.179 E 6.60 1.184 S 6.80 1.187 g I.14+00 , 7.00 1.191 7.10 1.195 7.40 1.200 7.60 1.205' v 7.80 1.208 8.00 1.210 1.10f00 8.20 1.210 8.40 1.208 0.00+00 2.00+00 4.00+00 8.00+00 8.00+00 1.00+01 8.60 1.204 8
COREHEIGHT(FEET) 8;8 lg 9.20 1.181 9.40 1.177 9.60 1.180 9.80 1.186 10.00 1.193 10.20 1.198
FIGlRE 3 - N(Z) FUNCTION FOR NIC8 AT 2893 MW FROM 3000 to 5000 MWD /MTU BURNUP TOP AIO BOTTOM 15 PERCENT EXCLUDED AS PER TECH SPEC 4.2.2.2.G HEIGHT. N(Z)
.(FEET) 1.80 1.173 )
2.00 1.167 2.20 1.161 2.40 1.153 2.60 1.146 2.80 1.140 3.00 1.134 3.20 l'.130 3.40 1.124~
1.2t+00 3.60 1.119 3.80 1.115
/\ 4.00. 1.114
/ \ 4.20 1.117 4.40 1.119 5
3,jg,go
[- 4.60 4.80 1.120 1.117 3 5.00 1.116 S ( 5.20 1.119 0 V 5.40 1.130
= 1.17+00 \ 5.60 1.142 T
- =
/ 5.80 1.154 E \ j 6.00 1.164
% \ / 6.20 1.172 3 \ 6.40 1.179
- "; 1
- 1 H00 / 6.60 1.184 5 6.80 1.187 5
f 7.00 1.191 ;
h / 7.20 ~
1.195 1.13+00 \ / 7.40 1.200
\ l 7.60 7.80 1.205 1.208 1.1t+00 vv *::: i:!!
8.40 1.208 0.00+00 2.00+00 4.00+00 6.00+00 8.00+00 1.00+01 8.60 1.204 8'8 "
COREHEIGHT(FEET) ,0 9.20 1.181 9.40 1.177 9.60 1.180 9.80 1.186 10.00 1.193 10.20 1.198 mm.____ _ _ __._ _ . _ . . _ . _ _ _ .
]
I FIGURE 4 - N(Z) FUNCTION FOR NIC8 AT 2893 MW FROM 5000 to 7000 MWO/MTU BURNUP TOP AND BOTTON 15 PERCENT. EXCLUDED AS PER TECH SiEC 4.2.2.2.G ,
s HEIGHT N(Z)-
(FEET) 1.80 1.173' ;
2.00- 1.167 2.20 1.161- i 2.40 1.153 2.60. 1.146 3 2.80 1.140 '
3.00- 1,134 3.20 1.130 3.40 1.124 3.60 1.119 1.21+00 3.80 1.1150
/ 4.00 1.114 j' T 4.20 1.117 4.40 1.119
= 1.18+00 [ / 4.60 1.120 J
4.80' 1.117
$ / ( / 5.00 1.116 t / \/ 5.20 1.119 d
/ V 5.40- 1.130
- U+00 \ / 5.60 5.80 1.142 3
[ 1.154 E 6.00 1.164
- ( I 6.20
"' 1.172 6.40 1.179 d 1.15+00' f 6.60 1.184 8
W
\ / 6.80 1.187
\ / 7.00 1.191 E g 7.20 1.195 I
\\O/ l 7.80 8.00 8.20 1.205 1.208 1.210 1.210 1.11+00 8.40 1.208 8.60 1.204 0.00+00 2.00+00 4.00+00 6.00+00 8.00+00 1.00+01 8.80 1.198 COREHEIGHT(FEET) 9.00 1.188 9.20 1.181 9.40 1.177 9.60 1.180 9.80 1.186 10.00 1.193 10.20 1.198
. l
. 1 3
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FIGlRE 5 - N(Z) FUNCTION FOR NIC8 AT 2893 MW i FROM.7000 to 15600 MWD /MTU BURNUP TOP A W BOTTOM 15 PERCENT EXCLUDED' AS PER TECH SPEC 4.2.2.2.G HEIGHT' .N(Z)- ..
(FEET) 1.80' .1.173 ;
2.00 1.'167 '
.I 2.20 1.160 -)
2.40 .1.153 j 2.60 l'.146 2.80 1.140 3.00 1.132 1.28+0D 3.20- 1.130 3.40 1.132 3.60 1.138 I I
A 3.80 1.140' 4.00 1.142 N 4.20' 1.141-1.24+00 (- 4.40 1.139 ;
oe. 4.60 .1.136 5 ! 4.80 1.135 g 5.00
- ) 5.20 1.141 1.158 g 5.40- 1.183
=
= 1.20+0D 5.60 1.202 .
5.80 1.216 !
/ 6.00 1.231 5 6.20 1.240 t
" '6.40 1.250 g 6.60 1.256 W \ 6.80 1.262 g 1.1E+00 \ 7.00 1.264 7.20 l'.265 7.40 1.263 7.60 1.260 V 7.80 1.255 8.00 1.249 1.12+00 8.20 1.242- :
8.40 1.234 0.00+00 2.00+00 4.00+00 6.00+00 8.00+00 1.00+01 8.60 1.224 COREHEIGHT(FEET) 8.80 1.213 9.00 1.197 9.20 1.185 9.40 1.178 9.60 1.180 9.80- 1.185 10.00 1.193 10.20 1.197-
- _ _ _ - _ _ = _ - -
=i i
FIGURE 6 - N(Z) FUNCTION FOR N1C8 AT 2893 MW l~ FROM 15600 MWO/MTU BURNUP TO EOL 1 TOP A W BOTTOM 15 PERCENT EXCLUDED- ;
AS PER TECH SPEC'4.2.2.2.G HEIGHT N(Z)-
(FEET) 1.80 1.166.
2.00 1.157 2.20 1.148 2.40 1.141 2.60 1.132 2.80 1.128 .
3.00 1.126 1' . 2 8 + 0 0 3.20 1.129- l 3.40 1.133 '
3.60 1.138 '
A 3.80 1.140 ,
4.00 .1.142 N 4.20 1.142 1 3,g .; \ 4.40.
4.60 1.139 1.136_ <
w [- 4.80 1.135 g / 5.00 1.141 .
- - 5.20 1.158 j g 5.40 1.183 .,
=
5.60 ' 1.202
= 1.20+00 5.80 1.216 l
- 6.00 1.231
=
6.20 1.240 s
6.40 1.250 g \/ 6.60 1.256 g V 6.80 1.262 ;
o
- 1.16+00 \' 7.00 1.264 7.20 1.265 k 7.40 1.263
\ ,s 7.60 1.260
\ / N/ 7.80 1.255
(/ 8.00- .1.249 1.12+00 8.20 1.242 8.40- 1.23( '
O.0C+00 2.00+00 4.00+00 6.00+00 8.00+00 1.00+01 .8.60 1.225 .;
COREHEIGHT(FEET) 8.80 1.213
. 9.00 1.198 9.20 1.185 9.40 1.171 9.60 1.167 9.80 1.170-10.00 1.177 10.20 ~1.181
t FIGlRE 7 - AXIAL FLUX DIFFERENCE LIMITS
AS A FUNCTION.0F RATED THERMAL POWER FROM 0 MWD /MTU BLRNUP. TO EOC FOR NORiH AcNA UNIT 1 CYCLE 8 i
l 1.20102 -
f 1.00+02 (.12.103) (+; 100 l
=
= ,
/ \ s
ilnacceptable 3 -
/ \- Operation 5 , Accepta )l.e \
, 6.00+01 w
i Om sti an
\ j 5 / \
w
\
4.00t01 (-2 7,50) (+2 ),50)
E .
U l
5
- 1, j
0.00f00
-5.00+01 -3.00+01 -1.00+01 .1.00+01 3.00+01 5.00+0i PERCENTFLUXDIFFERENCE(DELTA-1) i
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m