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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
,. _ ,,
1 4
4 4
Core Operating Limits Report (COLR)
North Anna Unit 1 Cycle 13 Pattern OG
)
i i
- l Virginia Electric and Power Company 1 ~e 9706170277 970609
, PDR ADOCK 05000338' p PDR
t .-
3 I i 1 .
1 .
1.0 . INTRODUCTION 4
l j The Core Operating Limits Report (COLR) for North Anna Unit 1 l Cycle 13 has been prepared in accordance with Technical
- Specification (TS) 6.9.1.7. The Technical Specifications affected by this report are listed below
i 3/4.1.1.4 Moderator Temperature Coefficient 3/4.1.3.5 Shutdown Bank Insertion Limit 3/4.1.3.6 Control Bank Insertion Limits 3/4.2.1 Axial Flux Difference 3/4.2.2 Heat Flux Hot Channel Factor 3/4.2.3 Nuclear Enthalpy Rise Hot Channel Factor and Power Factor Multiplier i
The cycle-specific parameter limits for North Anna 1 Cycle 13 for '
the specifications sisted above are provided on the following pages, and were developed using the NRC-approved methodologies specified in Technical Specification 6.9.1.7.
I i
~l l
j N1C13/OG COLR May 1997 Page 2
4 2.0 , OPERATING LIMITS 2.1 Moderator Temperature coefficient (TS 3/4.1.1.4) '
ll 2.1.1' The moderator temperature coefficient (MTC) limits are:
The BOC/ARO-MTC shall be less positive than or equal to !
+0.6E-4 .Ak/k/"F below 70 percent of RATED THERMAL POWER.
The BOC/ARO-MTC shall be less positive than or equal to 0 (zero) Ak/k/*F at or above 70 percent of RATED THERMAL POWER. '
The EOC/ARO/RTP-MTC shall be less negative than -5.0E-4 Ak/k/ F.
2.1.2 ~ The MTC surveillance limits are: !
The 300 ppm /ARO/RTP-MTC should be less negative than or equal to -4.0E-4 Ak/k/ F. )
l The 60 ppm /ARO/RTP-MTC should be less negative than or equal to -4.7E-04 Ak/k/ F.
where: BOC - Beginning of Cycle ARO - All Rods Out EOC - End of Cycle RTP - RATED THERMAL POWER 2.2 Shutdown Bank Insertion Limit (TS 3/4.1.3.5) 2.2.1 The shutdown rods shall be withdrawn to at least 225 :
steps.
l 2.3 Control Bank Insertion Limits (TS 3/4.1.3.6) .
2.3.1 The control rod ;anks shall be limited in physical insertion as shown in Figure 1.
s N1C13/OG COLR May 1997 Page 3
. .- .~ . .- _ _ , - - - - - _ - . . . . . . _ . -.. . _ _ .
i .
1 1
2.( Axial Flux Difference (TS 3/4.2.1) 2.4.1 The AXIAL FLUX DIFFERENCE limits are provided in Figure 2.
l
- l 2.5 Heat Flux Hot Channel Factor-FQ(Z) (TS 3/4.2.2) l I The Fg(Z) limits are:
l 2.5.1 '
i 2.19 Fg(Z) 5 ----
Fg(Z) $ 4.38
THERMAL POWER l where: P = ------------------- , and ,
RATED THERMAL POWER l i
K(Z) is provided in Figure 3.
2.5.2 The Fg(Z) surveillance limits are:
2.19 K(Z)
F g(Z)M $ ---- * ----
for P > 0.5 P N(Z)
K(Z)
Fg (Z) M $ 4.38 * ---- for P 5 0.5 N(Z)
N1C13/OG COLR May 1997 Page 4
l .
4 THERMAL POWER where: P = ------------------- ,
RATED THERMAL POWER
]
K(Z) is provided in Figure 3, and N(Z) is a non-equilibrium multiplier on Fg(Z)M to account for power distribution transients during normal operation, provided in Table 1 and plotted in Figures 4 through 10. The top and bottom 15% of the core is excluded per TS 4.2.2.2.G. I 2.6 Nuclear Enthalpy Rise Hot Channel Factor - FAH(N) and Power Factor Multiplier (TS 3/4.2.3) :
FAH(N) $ 1.49 * {1 + 0.3 * (1 - P) }
THERMAL POWER where: P = -------------------
RATED THERMAL POWER I
1 l
i l
- I l
L 1
I..
N1C13/OG COLR May 1997 Page 5 i
- j. ;
- =
3 a
Table 1 i^
.NIC13 NORMAL' OPERATION N(z)
I l Height Node (feet) 0 to 1000 1000 to MWDMTU MWDNTU MWI.WMTU 3000 3000 to 5000 5000 to 7000 7000 to 9000 9000 to 181 .
MWDMTU MWDIMTU MWDMTU MWDMTU 10 10.2 1.078 1.078 1.157 1.157 1.157
- 11 10.0 1.157 1.139 1.086 1.086 1.157 1.157 1.157 1.157 1.141 l 12 9.8 1.094 1.094 1.156 1.156 1.156 j 13 9.6 1.156 1.142 1.102 1.102 1.155 1.155 j 1.155 1.155 1.144 '
g 14 9.4 1.109 1.109 1.154 1.154 1.154 j 15 9.2 1.154 1.145 1.113 1.113 1.157 1.157 .
( 16 1.157 1.157 1.147 9.0 1.117 1.117 1.160 1.160 1.160 1.160 i 17 8.8 1.120 1.153 1.120 1.167 1.167 1.167 i 18 8.6 1.167 1.160 l 1.120 1.120 1.175 1.175 1.175 1.175 1.165 i 19 8.4 1.124 1.124 1.184 1.184 1.184 1.184
{ 20 8.2 1.134 1.169 :
1.134 1.191 1.191 1.191
} 21 8.0 1.191 1.174 1.14S 1.145 1.197 1.197 l 1.197 1.197 1.180 22 7.8 1.155
- 1.155 1.205 1.205 1.205 1.205 1.187 23 7.6 1.162 1.162 1.209 1.209 1.209 1.209 i 24 7.4 1.192 1.167 1.167 1.211 1.211 j 1.211 1.211 1.194 25 7.2 1.169 1.169 i 1.211 1.211 1.211 1.211 j 26 7.0 1.168 1.194 1.168 1.208 1.208 1.208 27 1.208 1.192 2
6.8 1.165 1.165 1.206 I 1.27f 1.206 1.206 1.190 28 6.6 1.160 1.160 1.201 1.201 1.201 1.200 l 29 6.4 1.157 1.186 i 1.157 1.194 1.194 1.194 j 30 1.193 1.180 6.2 1.154 1.154 1.183 j
' 1.183 1.183 1.183 1.172 31 6.0 1.150 1.150 )
1.173 1.173 1.173 1.172 i 32 5.8 1.165 i 1.145 1.145 1.161 1.161
- 1.161 1.161 1.158-33 5.6 1.138 1.138 1.147 1.148 1.148 1.155 j 34 5.4 1.129 1.155 1.129 1.134 1.134 1.134 j 35 1.149 1.149 5.2 1.114 1.114 1.117
)
1.119 1.119 1.139 1.139 !
i, 36 5.0 1.110 1,110
- 1.112 1.111 1.111 1.130 37 4.8 1.118 1.130 1.118 1.118 1.109 1.109 38 1.123 1.123 t 4.6 1.128 1.128 1.128 I 1.110 1.110 - 1.122 1.122 39 4.4 1.136 1.136 1.136 1.112 1.112 1.126
- 40 4.2 1.126 1.143 1.143 1.143 1.116 1.116 1.129 1.130 1 41 4.0 1.149 1.149 1.149 1.122 1.122 1.131 i 42 3.8 1.131 1.155 1.155 1.155 1.127 j 1.127 1.131 1.130 43 3.6 1.163 1.163
' 1.163 1.131 1.131 1.131 44 3.4 1.129 1.175 1.175 1.175 1.132 1.132 1.132 1.128 s 45 3.2 1.190 1.190 1.190 1.135 1.135 1.135 i 46 3.0 1.131 1.203 1.203 1.203 1.141 1.141 l
! 47 1.141 1.136 2.8 1.217 1.217 1.217 i
1.150 1.150 1.150 1.1,46 48 2.6 1.229 1.229 1.229 1.160 1.160 1.160
)
49 2.4 1.155 )
1.241 1.241 1.241 1.170 1.170 1.170 1.163 50 2.2 1.252 1 252 l
1.252 1.179 1.179 1.179 51 2.0 1.171 ;
1.262 1.262 1.262 1.188 1.188 52 1.188 1.179 1.8 1.271 1.271 1.271 1.196 1.196 1.196 1.186 i
N1C13/OG COLR May 1997 lage 6 l
L
Figure 1 Control Rod Bank Insertion Limits
- FULLY WITHDRAWN = 225 230 1.624. 225) 210 / "
200 190 (1, 1941 180 C Bank [
170 /
160 [
z 150 /
l _
140 [
E $ 130 D Benig [
h 120 ,
[
110 [
@ 100 [
O 90 '
! O 80 70 .
60 50 40 30 20 10 0 048 01 O 0.1 0.2 0.3 0.4 0.5 0.6 0.7 0.8 0.9 1 FRACTION OF RATED THERMAL POWER 6
N1C13/OG COLR May 1997 Page 7
- . I
. j l
l
. Figure 2 4
N1C13 Axial Flux Difference Li: nits 1
120 l l
i 110
( 12,100) (+6, ' 00) 100 ,
Unacceptsble 0mration 90 Unareptabie i
AGG6 Tumble Operation Opermiion i
i i 80 i u
l
! E 70 I i
l I i
60 -
, \
j l
e \
- o (-
- 27, fiO) (+20, 50) y 50 ,
e :
2 1 oI 40 30 20 i 10 4
'i 0
-30 -20 10 0 10 20 30 Percent Flux Difference (Delta-1)
NIC13/OG COLR May 1997 Page 8
. -- _ _ . . _ m . _- . .__
9 Figure 3 K(Z) - NORMALIZED FQ AS A FUNCTION OF CORE HEIGNT 1.2 1.1 1
(6,1.0)
^
0.9 Q 0.925) 0.8
~
N 3
- u. 0.7 8
N 3
4 0.6 E
cc o
2 10.5 ti u
0.4 ,
0.3 0.2 0.1 0
0 1 2 3 4 5 6 7 8 9 10 11 12 CORE HEIGHT (FT)
N1C13/OG COLR May 1997 Page 9
tj -
~
I i =
1 Figure 4 N1C13 NON-EQUILIBRIUM MULTIPLIER 0- 1000 MWD /MTU BURNUP 1.300 1.250 1.200 1.150 z
1.100 r
1.050 1.000 2.0 4.0 6.0 8.0 10 0 12.0 CORE HEIGHT, FT N1C13/OG COLR May 1997 Page 10 i.
t .. .
Figure 5 N1C13 NON-EQUILIBRIUM MULTIPLIER 1000 - 3000 MWD /MTU BURNUP 1.300 l
l h 1 1.250
)
l l
1.200 l 1
I i
h 1 .150 e 1 R
E 1.100 -
\
~
s 1.050 l 1.000 0.0 2.0 4.0 6.0 8.0 10.0 12.0
( CORE HEIGHT, FT i
N1C13/OG COLR May 1997 p
i
. . = ~ . . . . . . . - ~ . . ~ . . -- . . . . . _ . . ~ . - . ~ . - - . . - . - . - . . . . . . . - . . _ - . - . - .
l l'e
Figure 6 N1C13 NON-EQUILIBRIUM MULTIPLIER i
3000- 5000 MWD /MTU BURNUP 1.300 c
1 1.250 \
h 1
i i
1.200 l 1
l 1.150 "
1.100 1.050 1.000 2.0 4.0 6.0 8.0 10.0 .
12.0 CORE HEIGHT, FT N1C13/OG COLR May 1997 Page 12
- e .. ,
l ,
Figure 7 4
l N1C13 NON-EQUILlBRIUM MULTIPLIER 5000 -7000 MWD /MTU BURNUP I
1.300 1
4 1
)
4 1.250 1 1
i l i
4 i
l 1.200 5
. \
- I i
~
1.150 -
4 u.
I a
s, 1 1.100 i
1 a
1.050 1.000 0.0 2.0 4.0 6.0 8.0 10.0 12.0 CORE HEIGHT, FT N1C13/OG COLR May 1997 Page 13
4 /. . . ,
e i - Figure 8 i
N1013 NON-EQUILIBRIUM MULTIPLIER 7000 - 9000 MWD /MTU BURNUP 1.300 i.
i i
1.250 d ,
1 1 8 4
)
i 1.200 n
i I
i i
i 1.150 k
k '
J t
1.100
., 1 l
J 4 .
1 I
1 1.050 l
l l
I 1.000 0.0 2.0 4.0 6.0 8.0 10.0 12.0 CORE HEIGHT, FT
- N1C13/OG COLR May 1997 Page 14
- 1. . - _ - . . _ . -.
rs . . ,
. Figure 9
- NiC13 NON-EQUILIBRlUM MULTIPLlER 9000- 18100 MWD /MTU BURNUP 1.300 4
1.250 .l l
b l l [
1.200 i
~
1.150 R
f 1.100 1.050 1.000 0.0 2.0 4.0 6.0 8.0 10.0 12.0 CORE HEIGHT. FT N1013/OG COLR May 1997 Page 15
.. - l Figure 10 ,
N1C13 NON-EQUILIBRIUM MULTIPLIER 18100 MWD /MTU to EOC ;
1.300 1.250 I
l 1.200
\ 1 I / -
4 1.150 '
g
\s i
/
1.100 1.050 I
I 1.000 0.0 2.0 4.0 6.0 8.0 10.0 12.0 CORE HEIGHT, FT NiC13/OG COLR May 1997 Page 16