ML20138J898
| ML20138J898 | |
| Person / Time | |
|---|---|
| Site: | La Crosse File:Dairyland Power Cooperative icon.png |
| Issue date: | 12/12/1985 |
| From: | DAIRYLAND POWER COOPERATIVE |
| To: | |
| Shared Package | |
| ML20138J850 | List: |
| References | |
| NUDOCS 8512180113 | |
| Download: ML20138J898 (28) | |
Text
-.
- 32aa -
POWER DISTRIBUTION LIMITS-MAXIMUM AVERAGE FUEL ASSEMBLY EXPOSURE LIMITING CONDITION FOR OPERATION 4.2.4.2.5 The maximum average exposure of any fuel asse 'bly not on the periphery of the core shall be limited to 18,000 MWD /MTU.
l APPLICABLILITY: OPERATION CONDITION 1.
ACTION:
With the maximum average fuel assembly exposure of any nonperipheral assembly greater than 18,000 MWD /MTU, be in at least HOT SHUTDOWN with the main steam l
line isolation valve closed within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> and in COLD SHUTDOWN within the next'24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
SURVEITfANCE REOUIREMENT 5.2.17.5 The maximum average exposure of each fuel assembly not on the periphery of the core shall be determined to be less than 18,000 MWD /MTU by l
calculation at least once per 31 EFPD.
l Amendment No. 11, 16, 20, 26, 28, 8512180113 851212 ADOCK 050g9 DR L
t
- I
- 32gg -
POWER DISTRIBUTION LIMITS
~~ BASES FOR SECTION 4.2.4.2 AND 5.2.17 LINEAR HEAT GENERATION RATE - (Continued)
For Type I and Type II (A-C) fuel,.the orginial design LINEAR HEAT GENERATION RATE specified by the fuel manufacturer was conservatively reduced to 11.94 kw/ft to account for the effects of densification, power spikes and-
~
[
manufacturing factors. For Type III (ENC) fuel, the design LINEAR HEAT GENERATION RATE of 11.52 kw/ft'is also calculated with design conservatisms thct are larger than the calculated axial densification effects plus manufacturing tolerances and power spike effects, Reference 6 and 7.
'The daily requirement for-surveillance of the core LHGR above 25% of RATED THERMAL POWER is sufficient since power distribution shifts are very slow when there have not been significant power or control rod changes. The surveillance of core LHGR after power increases > 15% of RATED THERMAL POWER will assure that significant increases in LHGR are determined.
4.2.4.2.5 and 5.2.17.5 Maximum Average Fuel Assembly Exposure
References:
8, 9, 10, 11 and 12.
Fuel cladding' integrity is a function of many parameters including fuel exposure, pellet clad interaction, THERMAL POWER, rate of change in power density, coolant chemistry, etc. Therefore, limiting fuel exposure to 18,000 MWD /MTU.in the non peripheral fuel assemblies which experience higher than average power densities and rate of change of power will give additional assurance that the condition of the fuel during operation will be satisfactory. It is not necessary to limit exposure in the peripheral core locations since operating experience at LACBWR has shown that the 28 peripheral fuel assemblies have a much lower rate of failure than the 44 interior fuel assemblies. This trend has been attributed to the lower -power density at these locations, and the minimal effects of control rod movements which cause local power peaking in the fuel rods near the tips of the control rods.. The outer' control rods are fully withdrawn at the beginning of cycle (BOC) and remain withdrawn during normal cycle operations.
3 Amendment No. 11, 16, 20, 26,
s
-s.
- 32hh -
POWER DISTRIBUTION LIMITS BASES FOR SECTIONS 4.2.4.2 AND 5.2.17
. Maximum Average Fuel Assembly Exposure -(Continued)
Pellet-clad interaction is a well known and documented contributing factor to fuel rod failures.. The presence of pellet cladding interaction has been identified in. post-irradiation examinations of fuel rods removed from LACBWR fuel assemblies. Fuel rods removed from fuel assemblies with average exposure up. to 14,700 MWD /MTU have been examined. The strength, ductility, and condition of the cladding in these rods was found to be adequate as determined by mechanical tests. The examination further confirmed that power history of the rods is of prime importance, though not the only factor in contributing to
. fuel rod failure. During operation the rate of withdrawal of control rods, when the THERMAL POWER is above 25% of RATED THERMAL POWER, is reduced from that experienced during operation prior to Cycle 5 which also significantly reduces the stresses in the fuel clad.
Minor clad defects that may occur would be expected to develop very slowly and the consequences of such failure would be minimal.
Surveillance and limitations on coolant and off-gas activity will assure that operation does not continue with significant quantities of failed fuel.
References:
1.
" Technical Evaluation Adequacy of La Crosse Boiling Water Reactor Emergency Core Cooling System", Report SS-942, Gulf United Nuclear Corporation, May 31, 1972.
2.
" Review of Densification Ef fects in La Crosse Boiling Water Reactor",
Report SS-1085, Gulf United Nuclear Corporation, May 15, 1973.
3.
NRC Safety Evaluation Report, Letter, Reid to Madgett, dated August 12,
.1976.
4.
"ECCS Analysis for Type II and Type III Fuels for the La Crosse Boiling Water Reactor", Exxon Nuclear Company, Inc., XN-NF-77-7, March 1977.
- 5. '" Transient Analysis for LACBWR Reload Fuel", Response to Question 4, Nuclear Energy Services, Inc. Report 81A0025, February 18, 1977.
Amendment No. 11, 16, 20, 26, 28,
8
- 3211 -
POWER DISTRIBUTION LIMITS BASES FOR SECTIONS 4.2.4.2 AND 5.2.17 References - (Continued)
- 6. '" Description of Exxon Type III Nuclear Fuel for Batch 1 Reload in the
- LACBWR", Dairyland Power Cooperative, LAC-3929, May 17,1976.
- 7.. Exxon Nuclear Co. Letter, J. A. White to C. W. Angle,
Subject:
MAPLHGR Limits for Type I (Allis-Chalmers) Fuel, dated June 22, 1977.
8.
DPC Letter, LAC-6846, Linder to Ziemann, dated April 1,1980.
- 9.. DPC Letter, LAC-7572, Linder to Crutchfield, dated June 1,1981.
10.
DPC Letter, LAC-8109, Linder to Crutchfield, dated February 23, 1982.
11.
DPC Letter, LAC-8131, Linder to Crutchfield, dated March 4, 1982.
12.
DPC Letter, LAC-11318, Taylor to Zwolinski, dated December 12, 1985.
l (Next page is page 33)
Amendment No. 20, 26, 28,
W A
l TABLE I FUEL FEeFORMANCE tm T5'E LAchit l'
CYCLF. 4 CYCLE LA CYCLE 2 CYCLE 3 CYCLE 4 CYCLE 5 CYCLE 4 CYCLE 7 i CYCLE 4 CYCLE 9 I
i j
C0kDITton
!! J"LY 67-14 OCT. 72-25 JUNE 73-Il DEC. 73-II AUC. 75-9 MAR. 78-25 MAY 79-Il J AN. S t-l 4 JUN. 82=
5 JAN. 84* l r
l 19 AUC. 72 30 MAa. 73 3 Nov. 73 9 MAY 75 II MAY 77 25 MAR. 79 9 NOV. 80 9 apt. 82 1 5 MnV. 83 11 a.AA. 85 l' i
i i
l l
l Coal AVC. EXFO$U$F IMWD/MTU) 0.000-9.968 8.667-11,107 6.251-7.953 3,928-II.269 5,906-12.833 5.763-9.729 4.203-18,542 6,528-12.4881 6,nI3-12.521 6.830-13.6281 1
Il
, CYCLE LENCTu IMWD/MTU) 9.968 2.440 1.702 7.341 6.927 3.966 7.339 5.953 5.708 6.798
.I I
I l-l MAX. SOC ASSEMBLY AVC. EXP.
0 12.810 15,300 15.660 11.580 12.589' 13.065 13.247 14.134 l
14.609 l
l MAX. EOC ASSEMBLY AVC. EXF.
12.810 15,770 16,740 28.532 19.642 14,889 16.688 17.196 18.490 20.126 l
- OF ASST. DISCM.
8 26 25 25 32 28 24 34 24 32 l
i AVC. EIFOSURE OF DISCH.
II 490 14.360 11.591 15.530 16.459 13.966 14.872 16.085 17 ci3 17.702
- OF AS$Y. DISCH. WITN I >t5.000 0
to 3
9 27 0
12 32 22 32 r
- OF ASST. DEFECTtyt 8 FROSABLE -
20 23 10 26 17 I Fa08ABLE I
O O
- OF ASSY. WITM VIS!$LE DEFECTS I
15 11 4
6 7
0 I
0 O
MAX. # OF VIS!BLY DEFECTIVE RODS I
9 8
6 9
4 0
1 0
0 PER ASSEMBLY TOTAL # OF v!$18LY DEFECTIVE ROD 3
42 36 18 19 12 0
1 0
0 l
lESTEMATIO TOTAL # OF DEFECTIVE ROD NA 47 48 24 40 22 I
I-0 0
NO. OF AS$Y. WITH StCNIFICANT FUEL 0
0 0
0 3
0-0 0
0 0
DISPLACED DURING OFERATION AVC. EXPOSURE OF DEFECTIVE ASST.
11.490 13.986 11,190 16,691 16.774 13.880 16.688 11.006 NA NA EXF. RANCE OF DEFECTIVE 455Y'S
!!.034-12,134 12.264-15.205 2.200-15.300 13.52A-21.532 82.042-19.642 11,925-14.889 NA NA NA NA MAX. EXPOSURE OF C00D ASSY.
32.810 15.770 16,740 18.982 17.361 14.713 16.658 i.17.196 18.690 20.126 SCRAMS WHILE AT FQWER NA 4
7 14 9
12 14 13 4
7 s
COLD SKUTDOWNS NA 2
2 5
5 5
6 3
6 I
8
~
TOTAL # CF STAATUFS/TO HEATINC 20/8 53/27 32/11 23/7 50/29 45/28 26/13 34/20 1
RANCE ONLY 5
FUIL TYFES tt CF AS$Y/TYFE) 72/I 72/I 48/t. 24/11 24/t. 48/I!
72/11 40/11,32/!!!
2/I.12/It.58/It!
2/t. 70/tti 72/t!!
72/tt!
a 1
2
a TABLE 1 - (Continued)
FUEL PERFORMANCE IN THE LACRWR i
CYCLE 4A CVCLE 2 CYCLE 3 CYCLE 4 CYCLE 5 t
CYCLE 4 CYCLE 7 CYCLE 8 CYCLE 9 l
CONDITION 84 OCT. 72-25 JUNE 73-21 DCC. 73-It AUC. 75=
9 MA9. 78- ! 25 MAY 79-II JAN. 81=
4 JUNE $2*
5 JAN 84 - l 30 MAR. 73 3 NOV. 73 9 MAY 75 Il MAY 77 25 MAR. 79 9 Nov. 80 9 Ape. 82 5 Nov. 43 Il MAR 85 I
o STARTUr$ FROM COLD $HUTDOWN 3
6 6
6 7
i 4
7 8
i ROD MOVEMENT RE$ta!CTgon$
tod inter-No rod inter-No red inter-No rod inter. No rod inter-No rod inter-lNo rod inter = I No rod inter- : No red inter-I changes allowed changes allowed changes a!! owed changes changes allowed changes allowedlchannes allowed" changes allowed changes allowedl at fell power allowed POWER ESCALATION RESTRICTIONS Above 101 Power Above 10% Power Above 10%
Above 10%
Not startune Not startupe lNot startune Not startuns Not startune l
lt/ Min. With 10 !!/ Min. with to power 101/hr.
Power 101/hr.
51/hr up to 501 SI/hr up to 50% SI/hr up to SI/hr up to 502; 52/hr free -
[
Min. Hold After ein. hold after After July 1974 Also, on power.
power.
502 power.
power.
?20t to 502 power Each 51 each 51 increase. reduced to !!/hr tattial II/hr above II/hr above
!!/hr above
!!/hr above
'It/hr above 502 increase.
Alse 52/ Day above 601 power.
escalation of 502 power.
501 power.
502 power.
50% power.
power.
above 57% power
- cycle, on first Also, on initial 101/ day from cold startups cold startune Cold startune Cold startene Celd startues escalation of escalattoa of 40! to 602 tot / day from not/ day from 52/hr up to
' 402 power.
202 Je 502 power 51/hr up to 52/hr free -
fuel cycle.
cycle. ICI/ day and SI/ day 30% to 502 302 to 503 403 power.
free 402 to 601 above 60%
and SI/ day and 52/ day lot / day free tot / day free II/hr free 502 and 51/ day above power.
above 50%
above 50%
40% to 6CE.
40% to 601.
to 601.
60% power.
power.
power.
52/ day abcve 5t/ day above 7.51/ day above END OP CYCLE CONDITIONS:
60% power.
60% power.
601 power.
70WEa 981 821 851 561 49%
761 781 893 671 1
1 0FF=CAS ACTIVITY AFTER 150 FT3 a900
- 720
~450
-1.000
-290
-200
-320
-165
-70 not. DUP TAWK (C1/ DAY)
(-860)a
(.3gg}a
(.I 750)*
(~580)*
(-361)*
(-402)*
(~182)*
(-102)*
FRIMARY SYSTEM CROS$ 8/V
-4.0
-2.1
-2.0
-13.0
-3.1
.8 1.1
.55
.22 ACTIVITY (WC1/g)
(* 2.5)*
(-2.3)*
(-22.8)*
(-6.2)*
(~1.0)*
(~l.4)*
(~.60)*
(~.32)*
PRIMARY SYSTEM 1-L31
-49.9E-3
~47.9E-3
~84.7E-3
~37.4E-3
~9.32-3
- 2.18-3 3.98-)
- .8E-3
- .6t*3 ActTIVITY (vC1/g)
(-57.2E-3)*
(-16.9E-3)*
-( 6 5. 4 E-3 ) *
(-18.6t-3)*
(-2.7t-3)*
(-2.4t-3)*
(~.88t-3)*
(~.98-3)*
PRIMARY SYSTEM DOSE
~
~
-3.92-2
-1.5t-2 1.7t-2
.9t-2
.7E-2 squ!VAttsT I-83t
(~7.8t-2)
(-1.9t-2)*
(-2.lf-2)*
(.99t-2)*
(-l.ot-2)*
ACTIVITY (vC1/3)
PRIMARY $YSTEM 4 ACTIVITY
-3.5E-6
-I.2E-6
~3.St-6
~66.1t-6
.858-6
.08t-6
.10t-6
.05t-6
.075-6
(>C1/g)
- Values in parentheses are estimated for 991 reactor power.
m
.m,..
, TABLE II
'(
LACBWR Fuel Assemblies Discharged at End of Cycle 6 Fuel Assembly No.
Core Position Exposure, MWD /MTU 2-58*
F-1 16,688 2-56 A-6 16,658 2-67 E-l ~
16,320 2-66 E-10 16,310 2-54 F-10 16,309 2-37 L-5 15,734 2-71 A-5 15,704 12-50 L-6 15,589 2-64 B-9 15,452 2-57 K-2 15,407 I
2-61 B-2 15,230 2-60 K-9 15,223 l 2 7*
- C-6 14,334 1
3-6 *
- H-5 14,276 3-15* *
- D-7 14,167 3-18***
G-4 14,142 4
'(
3-14*
- D-4 13,974 3 -19*
- G-7 13,953 3 - 2 6*
- C-S 13,945 3-7 *
- H-6 13,884 24**
E-8 13,540 3-9 *
- F-3 13,533 3-23**
E-5 13,281 3-10**
F-6 13,275 Average exposure of discharged assemblies is 14,872 MWD /MTU.
- Assembly 2-58 probably contains a defective fuel rod as indicated by a weak dry sipping signal (s28 times background).
- These assemblies were returned to the LACBWR core at the beginning of Cycle C.
- These assemblies were returned to the LACBWR core at the beginning of Cycle 10.
t
o TABLE II LACBWR Fuel Assemblies Discharged at End of Cycle 7.
Fuel Assembly No.
Core Position Exposure, MWD /MTU 1-24 A-6 11,021 1-08*
A-5 11,006 3-28 C-8 17,196 3-5 H-3 17,166 3-31 B-7 17,128 3-2 K-4 17,067 3-30 8-4
.17,053 3-3 K-7 16,988 3-20 0-9 16,948 3-13 G-2 16,940 3-17 D-2 16,863 3-16 G-9 16,855 3-25 C-3 16,853 3-8 H-8 16,820 3-53 G-7 16,653 3-40 0-4 16,625 3-54 E-8 16,624 3-39 F-3 16,603 3-52 G-4 16,536 3-41 D-7 16,512 3-51 E-3 16,370 3-42 F-8 16,357 3-57 C-6 16,130 3-36 H-5 16,086 3-22 B-9 15,993 3-11 K-2 15,985 3-21 B-2 15,919 3-12 K-9 15,915 3-56 C-5 15,889 3-37 H-6 15,845 3-49**
F-6 15,263 3-44**
E-5 15,258 3-48**
F-5 15,216 3-45**
E-6 15,211 Average exposure of discharged assemblies is 16,085 MWD /MTU.
- Assembly 1-08 had a failed fuel rod.
- These assemblies were returned to the LACBWR core at the beginning of Cycle 10.
r WP-3
TABLE II LACBWR Fuel Assemblies Discharged at End of Cycle 8.
Fuel Assembly No.
Core Position Exposure, NWD/MTU 3-14 K-4 18,690 3-26 B-4 18,673 3-19 B-7 18,655 3-7 K-7 18,630 3-24 D-9 18,404 3-9 G-2 18,400 3-23 D-2 18,194 3-10 G-9 18,190 3-32 C-9 17,342 3-1 11 - 2 17,336 3-29 C-2 17.234 3-4 11 - 9 17,226 3-27 A-5 17,106 3-58 B-8 17,089 3-35 K-3 17,076 3-6 A-6 17,048 3-55 B-3 16,913 3-38 K-8 16,897 3-65 G-7 15,811 3-76 D-4 15,804 3-77 G-4 15,746 3-64 D-7 15,742 3-63*
F-3 14,605 3-71*
C-8 12,471 Average exposure of discharged assemblies is 17,053 HWD/MTU.
- These assemblics were returned to the LACBWR core at the beginning of Cycle 10.
a WP-3
l Table II LACBWR Fuel Assemblies Discharged at End of Cycle 9 Fuel Assembly No.
Core Position Exposure, MWD /MTU 3-75 G-9 20,126 3-66 D-2 20,123 3-73 G-2 20,011 3-69 D-9 19,993 3-80 K-4 19,786 3-61 B-7 19,747 3-62 K-7 19,731 3-79 B-4 19,718 3-78 B-8 19,181 3-33 L-5 17,921 3-34 L-6 17,905 3-50 E-10 17,876 3-43 F-1 17,871 3-47 E-1 17,860 3-46 F-10 17,859 3-68 A-6 17,811 3-72 A-5 17,806 3-67 B-3 17,309 3-74 K-8 17,297 3-70 K-3 17,186 4-9 D-4 16,249 4-12 G-7 16,414 4-8 G-4 16,352 4-13 D-7 16,348 4-17 E-6 16,346 4-4 F-5 16,341 4-5 E-5 16,340 4-16 F-6 16,339 4-18 H-6 15,663 4-3 C-5 15,653 4-6 H-5 15,582 4-15 C-6 15,563 Average exposure of discharged assemblies is 17,702 MWD /MTU WP3.6
g e A
B C
D E
F G
H K
L 3 Y7
~
3-Y3
_II.50 fl.f2 l
' 26 l
3-2/
3-21 3'/7
~
3 37 3-60
~
3-13 3-/
~
3-ll 15 9 13.1 3-16.1b h 75 lo.73
/4.19 15 11
^
I&ggf WR IfT l
If l
17 l
3 3-3-6l
'3-31
~
3-37 3-42
~ 3-5 3 35' b
iL.93
/h.
7 70 _ I 7 I@
'8 I
/6.37 14.40 7.G I7 17 I
6 I
13.13 3-30 3-63 3 '/o 3-by 3-M
~
3 3-4G
~
3-2.
A 17.o5 ixc Ib.63 1.3y s.32 I&.sy 7.41 17 o7 i
. 7@F3 l-S ~ [?'-
S4
~ 3-49l2 I
L___ lf t l
3-G7 3 'lY 3-YS 3-b?
~
3~34 3 70
~ 3-33 5
11 01 s.v1 it.1, 7.70 \\u Wzi tc2z _, 2ss 16.01 t.>is ii.so 1
?c7 gf2.y@F' l i
i
'9
@i 1-2 Y 3-7/
3 57 3-72
~
3-ys 3-y1
~ 3-73 3-37
~
_ rr i
h.*lt
/h.13 7.b9 W2/
d 24 7.70 Id%5' 3-7y 3-3V 11.D2 b.'l7_IM
(_94 1@LSJ l
4 1
l Ici I
3-31 3-71
~ 3-Y/
3-76
~
3-77 3 53
~ 3-78 3-3 17.13
- 7. */C lb.r/
t.3%
1.33 It.ls 7 55
~
It.99 hl I?
I I
ll l@l
/D l
361 3-21 3-71
~ 34tf 3-YZ 3-Bo 3-1
~
3-38 0
13.1 5 17.20
_ 7.b/
lb.41 14.36 7 70 16.82
/2.91
-~--~n ii
- p i
i A
i@
od--'
l l
9 3-22 3-32 3-10 3-71
~
3-12 3-lb 3-Y 3-/z 15 99 (2.37 lb.95 b.79 6.7C 16.3 6 13.11 15;1 1.
I
?f!
I IO
' ~ ' ' '
II.53
_. IIJO IN COi?C l' LUX MONITORS Q PLANT Fuel Assembly Number xxx Average Exposure (GWD/MTU) yyy LACBWR Core Configuration and Fuel Assembly Exposure
'at End-of-Cycle 7, April 9, 1982.
EOC Core Average Exposure 12,481 MWD /MTU.
A B
C D
E F
G H
K L
I 3-97
~
3-43
,,.,so us.su, m'ei I
3-51
~
3-29 3-23
~
5-93 3-$4
~
3-9 3-1
~
1 60 2
c.744 os.22I s3.pg, o
o otny ns.3g3 f.73cy 1 --~ /(9 s~ /tC i
/r i@l IT I
3-55 2 C7f 4-1 5
~
3 63 4-2
~
3-70
\\
3-35 3
12.93 c.v,91 o
7.vso 2550 o
4.96 i3. iso F 7 t@ F 8 1
3-24 43 J 74 af-V 4-51
~ 3I 4-4
~
3-JV 4
i3.tys O
- g. 3 0
o 7.339 F ?'
2 I@E~ 3 o
it.m I
I
/P I
3 27 y-7 1-79
~
4-8 1 72
~
3 73 4-q
~
3 10 4-10
~
3-33 5
- n. m o
un o
us ws i
?C9 LIMIZI o
2m o
asis i
i 9
I@l 2' O 3s 4 //
3-(/
9-12
~
3-hi 3 '?
Y-13 3-4J
~
4-1V 3-34 0
l'I.276 O
2 701 O
2iff 2693 0
2Coc O
II.s 73 LKy @L,,,,,S.J _1
.4 1
I Ic '
I 3-i1 4-25 3-64 4-14 4-17 3-45 4 -18 3-7 7
'3.fs3 O
s.335 o
O g.32; o
lign
@i ip9
~ i
//
i(f)I in i}
3-56 3-21
't-19 3 78 3-75 4 20 3 74 3-38 8
13 151 s.4 77 0
7 5V6
~
1453 O
CV70 12.f#9
~-
IE i
i i
I
?4 ih
?n I
9 3-9) 3 32 1-24 4 2)
~
4 22 3 -10 3-4 3-62 L732 I1374 I3 5Vo O
O II.215 I3.201 L796 I
9p 1
lQ 3-50 3-4C uts2s rn.3o;
,f thI CORE FLUX MON! TORS Q PLANT
" * ' ^ ** * 'Y "" * **
NORTH Average Exposure (GWD/MTU) yyy j_
b LACBWR Reload Configuration for Cycle 8.
The BOC j.
Core Average Exposure is 6,813 MWD /MTU.
t l
a l
~.
A B
C D
E F
G H
K L
3 17
~
3-13 M
/
i.filol I
N i
349
~
3-21 3-23
~ 3-13 31Y 3-9 3-/
~
3-l.a
~
E 7 63 17.13 l1.lf G.43 b.12 11.40 1].3g 9.4o 8_
I!D
- C IF:
l@f 17 l
l 1
I
_ IA
~
of-l 3-44 3-43 4-2
~
3 70 3-M~
345 3-47
~
b lb.91 Izsb 72 19.
7.3 (L.Vb 17.07 I
GM i
7'
'8 1
3-2.G
'y-3 3-74
~ 5 il 6
~ 3-77
'f-4
~
3-17
~
k IT.b7 7.2 b 1590 1.07 T.07
/Ctr 7.19 18.L1
~
\\@P3 I
h i
n p
1 l
In l
~
3-27 51 - 7 3-79
~
sl-3 3 72
~ 3 73 y-7 3-18 4-10 3-33
~
~
S n.i; s., z n.o2 7.gy l v.,,
iv.,,
_ 7.w iv.,2 s.is.
iv a PMM i
f2 i@
/
3.b1
~ _L_ _ _ 9 l@l F
I I
3-b y-il
~
3-61 tl-12.
3-41 y-13 3-42 y-ty 3-3y 17as b.Il M@_ 7.yy IV.11 lY.fo
- 7. *Lc ly.of b.Ib
_ fI GM 1 k. S __)
st.jk _ _L_--.4 st.jg 3-7 il 19 l
3-11 4-)J 3-49 sf-17 3W IE.b4
, 7 11 Q_
1.07 1 07
((:31 7.27 l1.43 h'3-71
~ 3-71 l
rp i
I 11 3-2r@I
~ 3-38 i
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.i i
s IN CORE FLUX MONITORS Q PLANT LACBWR Core Configuration and Fuel Assembly Exposure at End-of-Cycle 8, November 5, 1983.
The EOC Core Average Exposure is 12,521 MWD /MTU.
t Fuel Assembly Number xxx Average Exposurst (GWD/MTU) m i
s A
B C
D E
F G
H K
L 3-91 3-93 1sn 1La I ' 26 1
3-51{ 3-83 3-u 4-23 4-24 3-73 3 -89 3-60 9.63I
.4 J.19 O
0 140 L4JJ@113 liq I
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I 7
l t.
i 3-19 ~M 4-01 i~f8 4.YI
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11 0
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0 m
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l'Lia F~
N E-J i 2
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I
- t I
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'- 4-32 4-05 4-04 9-33
'- 4-06 4-3V 3-33.
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4-35 6f2w@LO_1 9.0'I
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2 it@_Q_
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J39 ill _1 7.34 7.42 0
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1 22 i
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I 4.G l 19.59 IN CORE FLUX MONITORS Q PLANT NORTH Fuel Assembly No.
xxx Fuel Exposure (GWD/MTU) m Core Configuration and Fuel Assembly Exposure at BOC-9 with Core E = 6830 MWD /MTU.
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IN CORE FLUX MONITORS Q o
Fuel Assembly Number xxx
- NORTH Fuci Exposure cwD/Mru. yyy LACBWR Core Configuration and Fuel Exposure at End-of-Cycle 9, March 11, 1985
'Ihe EOC Core Average Exposure is 13,628 MWD /MTU F
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