ML20043E677
| ML20043E677 | |
| Person / Time | |
|---|---|
| Site: | Hatch  |
| Issue date: | 06/07/1990 |
| From: | SOUTHERN COMPANY SERVICES, INC. |
| To: | |
| Shared Package | |
| ML20043E670 | List: |
| References | |
| NUDOCS 9006130270 | |
| Download: ML20043E677 (20) | |
Text
.
,[* .s L",' .' -
'~
- + * " ' ,,
"*d-
,[, ., ,
- U
. - v - .- ,. y,, .9, 7 -
.. ., p ;, , . .; . .n , ,
c
- - . , . . , - , * ,';* , +-
- 4, ,, , , , ..,; , 4 4 ., .- , , , e .f ,, . ? - .
Ik ' ', '
-
- f ',4
,s. .-
'4 .' , as k -~ % ,-. '. N * ,y ,,, ' , -
,=4 gi 5 - -
g .q' 4 L)a,. *, ' , ' ' , ' , . =w ** -#. ' ,J,-'
c,, ,' ' ,. . , .- :l
.,,.d'- ,[g ,
L_ < ^ ' V 7
. ,,.sh_-
-m >
bp. .',; .q\ s --
L.. ,.. s. , . .-
- @ 7., pc..,p; . . . s,w . .
..w. _ ,. .,.. .
g
. ; f .) ', 3' . -. e..
-4. v. . . . . , , ,
. (
.',.,4,.-.'J',., .ys .,3. , .( * <
,f .
.. , . j . y ',4 ;. , ; , + -l.. * j .g f' .,
- p_ s , ,g ,, , ,, . ; .
y , . - .y}
i -
- g . r *
\ p .
~~ .
^ g y, ,
, . *_ ... , , , . , g., ;. p ,;
- i V uM, .,A ,, iy ,:- _,9.,?",..,
i, n; M -#.
, , t ' ,; e, .% , t .i p t . n,
.,., , ,.) U ~ (.f. ,
p,. 3, '.f. l
= h. ,
-h ,
,, k$
,j ~*
-dd. ' 'ti .I -
... .h E[ ' [rO. 4) ' 'l Y
. , )*, '
w - , ,. t 5 ,g t, s-. -
' p. , , . . ., t .. g t/* ., 4, . .
a $e ,e : - g.' Qi g a y,, , g 5.# .a m
. ' ~ ' ,, y[j , ,hi!Y Jf ' -
,h; ,. y 4, ' 'Y , x ,T.
[ d' h ,)..' ~
- I
, .Nf, ',' ., , I . I. -
- $ 7 ?
'_ I' .',' . ~ i,'. '(*g, F _b ' ." . - f '
,f
.,[ t !$. ',( ,
.; - ,T '. .- .-%
~ -l . Lf ' ..lYb?%f .
.h T! r.h. .4W N. j', ,
&f[t: %))%k ,)WM$b; * ' lgg -f?l I ^ dW ;g [.i. Q' % %. 'JQ M . Q .. l ,y b ,J. D -
$ G,. 7 : Ia l 6",, ' ;.->s*.M dl i'*, h$bf l d' ' ' ' . ih-[k,' b*
,3 3 a ,<"
.i.p3 i.y kf p,# ' ' l
- h' '.
. }q ' f; ".T' .
1
- [f Q.f'k y li *E' p
- y,> FT' ,, Ig*4 , (,i. ' .,yE
. '$ . , ' -81
. . . g 4, y p _i e- .:'k. . rk- ' r./ +
{k. k[w'n w hk (
a n;.y, , e n n
^1 1 - ; 'h .;
'f'.
o w; m ..w p .. w ., n; w . g ,w.
O c. y ,p y v h y yg.1.w.5,;: % , n.
l .. E . h h N?.h.&nh... {.
w u. ~m - . h hMc h
, y . s a. h ? s Y u Y u r. 4.Ni Ws h ,.
w- h h w h w.
w h.0b m, k h'.
+ h . k h a
f Yl x..ye y_r ryv, ,... . .
- v. ..v.. 7
. 1
. . . , .._% . y,,.;, ,.
- c,.w -
+.e= --
}{ '
g ;' .
'.E .
i
...s , *. y .
l y ' .f...1 ? ' ' k..4e.
y' ; . ,
' f. - '. .
- u ,
[ N; (g- g
- y :
ns ..g ;j! g - ;
.;. n
, ~.. ,1.' g; ;
t .
e ..
EE 4 ' . '
- ' tu t.
c- ,
. N' ] '- ' . . ,
-k-
"k ' p t
&' & '9 ' ,[ ',:.g. . ~ \' '-
_ l' p? -/
1.. ,
q, -
' ~
- ;,. , s.
. i .*
y .
' .^ T
' ^
~ ' '
,f ., .
j: ,, .W' .,. y. . . . ,.~.
..; R . g-)... % , .
I . .
g I Edwin i Hatch l Nuclear Plant - Unit 1 I
I g
.I ..
CORE OPERATING LIM!TS REPORT l for g Operating Cycle 13' I
I:
g I:
- g
I Revision 0
- I:
3 i
Interof fice Correspondence (,n ngi;il\ nu ; d DAll : May 25, 1990 I RI : Core Operating Limits Report for Hatch I Cycle 13 file: fuel Cycle Technical Log: HL-ll10 sj IROM: S. J. Bethay i
.f 10: ALL UNIT 1 AND UNIT 2 TECINICAL SPEClflCATIONS HOLDERS By Amendment 168 to the Unit 1 Technical Specifications (TS), the NRC authorized relocation of certain fuel-related limits from the Technical Specifications to the adjunct Core Operating Limits Report (COLR). This letter transmits to all Unit 1 Technical Specifications holders a copy of Revision 0 of the Core Operating Limits Report for Hatch I Cycle 13. This ;
document should be utilized in conjunction with the Unit 1 Technical i Specifications as referred to in the Specifications.. Normally, the shift technical advisor (SIA) or reactor engineer will utilize this report.
I Where necessary, the fuel limits from the COLR have been included in plant procedures, l'
if changes to the core operating limits contained in this report are '
required, a complete revised COLR will be issued and the appropriate procedures revised. 4 l Amendments 168 (Unit 1) and 106 (Unit 2) removed several of the fuel-related figures (e.g., MAPLHGR, MCPR) from thd Technical Specifications, because the figures were included in the COLR. As such, I the figures should have been removed from the Technical Specifications and discarded when copies of the Technical Specifications were updated, please check your Unit I and Unit 2 Technical Specifications against the attached page change instructions to ensure the update was done properly.
If there are any questions regarding this report, please contact me ,
at extension 8 821-7392 or telephone number (205)-877-7392. !
t i ;
RDB/eb 000553 Attachment-c: NORMS !
i
, , . . .~
s .
1 l
AJTACHMENTTOLICENSEAMENCFENTNO.168 I i
I FACILITY OPERAllt;G LICENSE NO. OPR-57 DOCLET NO. 50-321 I
keplace the following pages of the Appencix A lechnical Specifications with 1
I the enclosed pages. The revised pages are identified by amendment nuinber and contain vertical lines indicating the areas of charge. ;
i i Remove l' ages Insert Pages Act.ive Page l, ist Ac t i ve l' age l is t 111 tii I x xi 1.0-7 x
1.0-7 1.1-6 1.1-6 1.1-7 1.1-7 1.1-8 1.1-6 3.3 5 3.3 5 3.3-6 3.3-6 3.3-7 3.3-7 3.3-9 3.3-9 I 3.3-15 3.3-16 3.3-16 3.3-15 3.3 16 3.3-18 f I 3.6-22 3.11-1 3.ll-le 3.6-22 3.11-1 3.ll-lo 3.11-2 3.11-2 3.11-2a --
3.11-3 3.11-3 3.11-4 3.11-4 !
3.11-4a 3.11-42 figure 3.11 1, --
Sheets 1 through 8 figure 3.11-3 I 1igure 3.11-4 Figure 3.11-6 6-15d 6-15d I
I I
.I .
I ,
t - - -
ATTACH. MENT,T,0_ LICENSE _ AMENDMENT NOS. 104 .LO5x _nd a 106 L
FACILITY OPERATING LICENSE NO. NPF-5 DOCKET NO. 50-366 I Replace the following pages of the Appendix A Technical Specifications with the enclosed pages. The revised pages are identified t,y amendment number and I
contain vertical lines indicating the areas of change. Corresponding overleaf pages are provided to maintain document completeness.
SemovoPages insert Pages
- Active Page List Active Page List
, 1 1 XVI XVI 1-2 1-2 2-1 2-1 B2-1 B2-1 B2-2 B2-2 R B2-3 B2-3
'3 B2-4 B2-4 B2-5 B2-5 B2-13 B3-13 3/4 1-4 3/4 1-4 3/4 1-14 3/4 1-14 3/4 1-15 3/4 1-15 3/4 1-16 3/4 1-16 3/4 1-17 3/4 1-17 3/4 2-1 3/4 2-1 3/4 2-2 3/4 2-2 3/4 2-3 3/4 2-3 3/4 2-4 3/4 2-4 3/4 2-4a ----
1/4 2-4h ----
3/4 2-4c ----
3/4 2-4d ----
3/4 2-4e - 3/4 2-41 ----
3/4 2-4j ----
t 3/4 2-4k ----
-a 3/4 2-6 3/4 2-6
-l 3/4 2-7 3/4 2-7 3/4 2-7a 3/4 2-7a 3/4 2-7b 3/4 2-7b - 3/4 2-7d 3/4 2-7c ----
3/4 2-/d ----
3/4 2-8 3/4 7-g 3/4 3-1 3/4 3-7 3/4 3-39
- I' 3/4 3-41 3/4 3-39 3/4 3-41
- I '
..7 ,._ _ _ _ _ . _ _ _ _ . . - . _ . _ _ _ _ . . _ _ _ _ . . _ . _ _ . _ _ _ _ . _ . _ . _ . . . _ _ _ . _ . _ . _ . _ _ _ _ _ . _ . _ . . __ _ _ _ _ .
h
. t a
E 899919 Pjages Insert Pages -
t 3/4.3 4? 3/4 3 47 3/4 10-2 3/4 10 2 8 3/4 1-3 B 3/4 1-3 !
B 3/4 2-1 B 3/4 2-1 0 3/4 P 2 8 3/4 2-2 0 3/4 P-3 8 3/4 2-3 8 3/4 2-4 8 3/4 2-4 ,
B 3/4 2-6 B 3/4 2-6 '
B 3/4 4-1 g 3/4 4 1 6-14d 6-14d- 4 i
I I <
l -
't i
{
PlHPj lI l
b l;
- ._._,,m..~_. - .
'I I
I
- I I
I GEORGIA POWER COMPANY EDWIN 1. HATCH NUCLEAR PLANT UNIT 1 FUEL CYCLE 13 CORE OPERATING LIMITS REPORT REVISION 0 I
I I
I I
I I
SOUTHERN COMPANY SERVICES, INC.
I: P. O. 80X 1295 BIRMINGHAM. AL 35201
I EDWIN I.' HATCH NUCLEAR PLANT UNIT 1 FUEL CYCLE 13 '
CORE OPERATING LIMITS REPORT
- 1. INTRODUCTION i
I This CORE OPERATING LIMITS REPORT for Hatch Unit 1 Cycle 13 is prepared in accordance with the requirements of Hatch Technical Specification 6.9.1.11. The core operating limits presented herein
- were developed using NRC-approved methods (References 1 and 2).
Results from the reload analyses for the General Electric fuel in !
l Hatch Unit 1 Cycle 13 are documented in References 3 and 4.
The following cycle-specific core operating limits are included in this report: 1
- 4. Operation with a Limiting Control Rod Pattern (for Rod Withdrawal Error (RWE)) !
(Technical Specification 3.3.F) '
s t
- b. Average Planar Linear Heat Generation Rate (APLHGR)
(Technical Specification 3 ll.A)
- c. Minimum Critical Power Ratio (MCPR)
I (Technical Specifications 3.11.C and 4.11.C)
- d. Linear Heat Generation Rate (LHGR)
(Technical Specification 3.11.B)
- 2. LIMITING CONTROL R0D PATTERN (Technical Specification 3.3.F)
Both Rod Block Monitor (RBM) channels shall be operable as specified in Technical Specification 3.3.F and when:
- a. THERMAL POWER is < 90% of RaiC0 fHERMAL POWER and the MCPR is less than 1.70, or
- b. THERMAL POWER is 2 90% of RATED THERMAL POWER and the MCPR is less than 1.40.
l REVISION 0 1
i I EDWIN l'. HATCH NUCLEAR PLANT-UNIT 1 FUEL CYCLE 13 CORE OPERATING LINITS REPORT I
I 3. APLHCR LIMIT (Technical Specification 3.ll.A)
I The APLHGR limit is given by the applicable rated power, rated flow limit taken from Figures 3-3 through 3 8, multiplied by the smaller of either: ,
- a. The factor given by figure 3 1, or
- b. The factor given by Figure 3 2.
For the fuel types whose APLHGR limits are shown in Figures 3 3 through 3-8, the APLHGR limit shown shall be applied to each axial g location in the fuel assembly.
- 4. MCPR LIMIT (Technical Specifications 3.ll.C and 4.11.C)
The MCPR operating limit (OLMCPR) is a function of fuel design, average scram time, core flow, number of operating recirculation loops, and core power.
4.1 Iyg Recirculation Looo Ooeration I for 25% s Power < 30%, the OLMCPR is given in Figure 4-1. For Power 2 30%, the OLMCPR is the greater of either:
- a. The applicable limit determined from Figure 4-2, or
.I
- b. The appropriate K p given by Figure 4-1, multiplied by the appropriato limit from figure 4 3 where the scram time dependence is given in Technical Specifications Section 4.ll.C.2.
I REVISION O 2
t WWIN 10 HATCH NUCLEAR PLANT I UNIT 1 FUEL CYCLE 13 !
CORE OPERATING LIMITS REPORT
]
I 4.2 Sinole Recirculation Looo Ooeration I for single leop operation, the MCPR operating limit shall be 0.01 l I greater than the two loop value which is determined as specified in Section 4.1, I
- 5. GGR_ LIMIT (Technical Specification 3.11.8)
The LHGR limit is 13.4 kW/ft for all GE7 fuel. The LHGR limit for GE8 and GE9 fuel is 14.4 kW/ft. There is no corresponding limit for the ANF 9x9 fuel .
6.
I REFERENCES
- 1. " General Electric Standard Application for Reactor Fuel,"
NEDE-240ll-P A-9, September 1988.
'l l
- 2. Letter, L. P. Crocker (NRC) to J. P. O'Reilly (GPC), " Issuance of Amendment Nos. 151 and 89 to Facility Operating Licenses DPR 57 i and NPF Edwin I. Hatch Nuclear Plant Units 1 and 2 (TACS ,
66524/66525)," dated January 22, 1988.
, 3. " Supplemental Reload Licensing Submittal for Edwin I. Hatch l Nuclear Plant Unit 1, Reload 12, Cycle 13 " GE Document 23A6504, Revision 0, April 1990.
l 4. "Edwir i_ Hatch Nuclear Plant Units 1 and 2 SAFER /GESTR LOCA Loss of Coolant Accident Analysis," NEDC-31376.,,E, December 1986, i
- 5. Technical Specifications Bases for Sections 3.3.F. 3.ll.A, 3.11.C, and 3.ll.B.
'I REVISION 0 3
HATCH 1 CYCLE 13 CORE OPERATING LIMITS REPORT REV!510N O I
e I ,
I :
o O$
E l C
- I !!!g I l i ,e f !I !Qi 8
+g n P.r 8
\
\ T
\ g g [qr-hf1 87
- s!
at 9
! $ m5 l;# [ 5 5 g5p a e w y m
-d' b'E y gs V i E .
l5 E &
I f' 3 hh'!!
f i l l l fi:i l ' '
lx
~
g a
g
- -- -- -- ,;' C
\
I -
s g
3 -
I g , , ,
! !! ! ! ! e l suvm.ow mou.o .. !
4-
an. a a.e 44 a.m-s - s, ssen At 4-.-aA-*Jo me- ---k-ew-- -was.- "---44-m-4* 4wes,=n&45-6 A- es&,e ^-o* bom' .4 . A na-mak-emn>s..aemA141mm*A I
I HATCH 1 CYCLE 13 CORE OPERATING LIMITS REPORT
- REV!510N 0 I -
I -
I I -
\ i i:
\s
$ - e k, u" o
- 4 g E I m.
3 ,
Ek I a r
5 _
s g ,^
l W 0 o 0
.i a a > - ,
k .
i Ig i
' o *
,s ,t .e.f. s.g,g s 2 in .ve . .-. . . . .( g I $ #5 555 b (-
3 J f* 10 .v e v . h
' ~
e o
. . . v' $ v' . $ f. v. g" -
.II!8 $. l i l. ;!i . !
! 8 g3
, .e .
pb b b E 4
^ N_ _ - ,
E.,,
C$ $$ $ 0 0
I ! ES E! Io $ !! I, - -------- 8 I I I l I I i i i 1 i g g : : : : : : :
d i 37 savnt WOA39 s WON 1dyn ANDOhldf 0 W BMOs I ...
4 i
D 14 m ,
- y UNACCEPTABLE O
z 13 1 OPERATION O o
12.6 o E -
o 8, V Tm 3 12--
' - C z- a
- 11.8, . in i ' I
- ] 11--~ --
LOW EXPOSURE i i
$ )f(
(O ooO COORDINATES :
- ' -< x s i X Y C pzg 3 *O o d -
0.0 11.5 10.4 \
t
< iO-0.2 2.0 11.5 11.8 t ACCEPTABLE if %$ eu 4.0 6.0 11.9 12.1 1
OPERATION : 1 3
y 3' oz 5-<
8.0 12.4 O z y
i 9- - 10.0 12.5 12.5 12.5 FUELTYPE- BP8DRB265H and P80RB265H i
- p 80 - MIL CHANNELS 8.4 ,
8' , . . . ** - -
\
0 5 10 15 20 25 30 35 40 45 i AVERAGE PLANAR EXPOSURE (GWd/st)
FIGURE 3-3 AVERAGE PLANAR LINEAR HEAT GENERATION LIMIT vs AVERAGE PLANAR EXPOSURE :
f f
1 L
o 14 m ~
i .
UNACCEPTABLE o --
4 z i OPERATION o 13 i O o
G
~
^
C S a l iE 3 12---
12.4 12.4; Q g@
g 6
3 , , n l
11.9 ; j G, c~QE b ~
- i 3 z- o E -
! LOW EXPOSURkl l ! l ! # E
-- E 8 11 ~ ' '
U ^^ N
- g. _.
) , COORDINATES .
i, i j to o o o zg
" O
! X Y !; Ozm C <Ec2
! 3 a
0.0 10.8 10.6
! ' 3 _. O O L < 10 ;
0.2 10.9 .
ACCEPTABLE ' ! W gn e 2.0 11.2 ;
' 2o
_ j 4.0 6.0 i2.5 11.8 -
- OPERATION : @ iz g-<-
i ,
}
8.0
~
12.1 l' O z
, 9-- l 10.0 12.3 .i ! i ,
y i 12.5 12.4 !'
FUELTYPE- BP80RB284H and P8DRB284H I
! ; i >
i
. i 1 80 - MIL CHANNELS I 8.5 8 .
I
.i
,' , . .i i
- i .
i 0 5 10 15 20 25 30 35 40 45 AVERAGE PLANAR EXPOSURE (GWd/st) i
. FIGURE 3-4 AVERAGE PLANAR LINEAR HEAT GENERATION LIMIT vs i AVERAGE PLANAR EXPOSURE g ~ - , . *~ ~ ~ - r - .--r- . , ,, . - ~ en
L
[
m 14 10.99 m i s UNACCEPTABLE 5
z ~
o 13 OPERATION 4 i l- 10.20_.Ju. O m O Z; j uj n _
. g a gg ;
12-
^
3x (9.7) (9.7) 9.42g g VOO E i O[g El
[ ,
11 S ,
(9.3) g $c m
s gz 2
N@NE
~
j k3 11~)
Z COORDINATES 8.63 3-g"0
' I
' h@tr X Y *0 5 r.o z en J
0.0 10.8 8.4 10.6*
(8'3)
-,,,}Qc _. O i s <. 10- 0.2 10.9 8.5 - ACCEPTABLE 7.85 @ go> $
r i'
2.0 11.2 8.7 I 4.0 "
6.0 11.5 11.8 9.0 9.2 OPERATION s' 2I !
~^
8.0 12.1 9.5 4 V g i 9 10.0 12.3 9.6 7.06 O z y '
l 12.5 12.4 9.7 ,
FUELTYPE-4 --
- 9 X 9 LFAs i 8.5 0 !
j -
80 - MIL CHANNELS '
(6.6)*
8 .. :- , ,, 6.28 .
1 0 5 10 15 20 25 30 35 40 45 uor,s:
} AVERAGE PLANAR EXPOSURE (GWd/st) }
"= =5 = $ = 1
- FIGURE 3-5 AVERAGE PLANAR
?"J ' 1""/,",y,'"" LINEAR HEAT GENERATION LIMIT vs :
1 AVERAGE PLANAR EXPOSURE i i !
i h
x -
1 g -
$ : , UNACCEPTABLE 12s N 5 -
OPERATION O 12N O t 11.8'
! 1 11.3 b l $ 11 O Go
! 3 ~
'O Tm j E : ;
+
- e EO ,
i t- 10 I
3 Er$ i i
k LOW EXPOSURE I 94 h (
\
E COORDINATES :
O 00 O l 9 --
-< r q l
$' 1 X Y l
I g
0~0 11~9 a0 O i l'
% 8:
i.0 12 2 i ACCEPTABLE .
,,,N ifjeu 5.0 12.5
!\ _
i 1a0 12.9 i OPERATION
~w?
i i y@ 5 -<
7- -
\
[ i o 2i ;
fruanese S3 " 3 s h ; 1967 HATCH 1 LTAs j
5 0 5 t
i
.10 15 20 25 30 35 40 45 50 AVERAGE PLANAR EXPOSURE (GWd/st) I t
4 FIGURE 3-6 AVERAGE PLANAR LINEAR HEAT GENERATION LIMIT vs AVERAGE PLANAR EXPOSURE i-i
i m
i m _
h z
- UNACCEPTABLE l 12 1 / ,za s
, OPERATION O l
@e 11.09 R
G E 11 - i m 3 --
j
, O oo x O Em 4
b 10;
! ' e EO l _ ,
y E -- $
l 2
J LOW EXPOSURE i
- 9.79: "4I i
tr 9 1._ C N TES 2
1 o3 on$,F o
i -
e _.
X Y -< I E r _.
CO zm I
d
< 8--
0.0 11.54 3 "o o ACCEPTABLE w
- &o9I
- i.0 11.52 ,
- 20 11.s4 4.0 i2.08 : OPERATION T 7 -
8.0 12.73 8 7
10.0 12.81 y g<
o
- ' __i ; , 2; 61 .-
l NELTYPE:l BD296A
\
l l 80 AML CHANNELS { ! !
! , t 5 . . . .. .. .
5.36 $> r O 5 10 15 20 25 30 35 40 45 50
. ; AVERAGE Pl.ANAR EXPOSURE (GWd/st)
'"**'^^""*"'""'
MOST UMmNG LATTICE AS A FUNCTION FIGURE 3-7 AVERAGE PLANAR !
r og AvsnAce nma- LINEAR HEAT GENERATION LIMIT vs :
AVERAGE PLANAR EXPOSURE
mm um amm nas em uma num nas sus sus mas-- mum . .
l i
- 1 l 13
! '3'8; '
E z
UNACCEPTABLE
!' ,z .
1 127 -
' OPERATION . O t
O i 11.79:
t p p LOW EXPOSURE ; i O g -
COORDWATES '
- O ,
oo i V Em I x X Y i i f !
G EO l' i 10 46. ; ;
- t-- 10- 0.0 11.85 g g -- g l ;
- g 02 11.92 j j j
- , ,. q z y l
_s 1.0 12.03
- _
!~
C gI 2.0 12.17
, 1 I
- j ,
3 m$, i I
O oOO !
! 'y ; 3.0 I
i _.s 4.0 12.35 12.56 ; i I l 8.96Y
[g o71k Ec 2 y
i
! 8:
- 7.0 EQ . jACCEPTABLE l :
g %y
! 13.15 !i "7Z
- 7- -
8.0 1324
' l OPEMTION ' -
I G
- : 9.0 13.31 i i
V g !
j ! O z i 10.0 13.41 l
, ! ! i y 4
6 -- -
12.5 13.50 i g NN!
l
} [ - l 16 M-150
- l ! 5.86 f ! >
5- ' , !
i 0 5 10 15 20 25 30 35 40 45 50 AVERAGE PLANAR EXPOSURE (GWd/st)
FIGURE 3-8 AVERAGE PLANAR LINEAR HEAT GENERATION LIMIT vs AVERAGE PLANAR EXPOSURE !
i
I GEORGIA POWER COMPANY !
- l EDWIN 1. HATCH NUCLEAR PLANT UNIT 1 CYCLE 13 l Core Operating Limits Report 8
-.2..... > .
l
- 5. g -
i I gg 1
~
l g i ee II
.g p
i t l 1 .
W m
lI*lEl
- ^
l .i .l ].
- gg g;. . _._. . . . _ . . . . .g g
!l '
l ...
'l li ii .
8 iii
.. g b
3 2 ; Ii 5, 5, 5, ii e-[ j l 1 I 1 I I I I i 4o t . I
._..- . . . . .. g ws mg M DZ l 9w-I LL. O
_ . _ _ . .. ._ - .. _ . . . . _ . . _ . _ _ _ _ . . _ . .g Z w l Q. W Q ' g . . . - . . _ . . . . _ _ . . _ _ . . . _. __. _. _ . . _ _ _ g m l h h n
~
/h. . . . g. .
.g S n do i A V. - '
~
l n u 6 ' + ' s ' N ' 4, ' o8 e's'+'s'Ne'en N N N N W N s a s - - - l %00 ~< d WOd (dM) Wandl1~lnW 031YW
%00 > d F %03 WOd WdOW~lO du l REVISION O 12 I
i m 1.7
'E , N FLOW RATE - +
! FOR Wc (% RATED CORE FLOW) 2: 40% l O ,
117 % j z ~ i
/, 112 %
MCPR(F)= MAX (1.20. MWc/100+BI) l o 1.6 - i ~ O
/ /,/ /[
- jg i MAX FLOW M Bf t-
~' ,- 1m% i 117.0 j o
-0.632 1.809 i (p
/'
/ /<ji 112.0
~
3 -0.002 1.747
- I ~ !
107.0 -0.586 I O a ! 4 e j [. l 102.5 -0.571 1.697 1.665 V S 4m ' l C E m
,4 z __ >
e L 3 N a N 1
~
, $ }
i i nN ! , q9 h!
't N m 12 FOR Wc (% RATED CORE FLOW) < 40% l
\ s N $5 A
%g
@(F)=(MWc/100+Bf)
*[1+0.0032(40Wc)] !
i 1.1 . 3 . l 6 ii!6 6 i !iie !. , i e i 4 a i e i . 30 40 50 80 70 80 90 6 6 6 i 100 110 120 CON FLOW (% rated) 3 FIGURE 4-2 i FLOW-DEPENDENT MCPR UMITS, MCPR(F) 4' I I
I HATCH 1 CYCLE 13 CORE OPERATING LIMITS REPORT REV!$10N 0 l i l MCPR Limit as function of Averoge Scrom Time I 1.3
~
7 I
- / ,
1.26 g l 1.27
/
I t
, 1.26 g >
~
. 1.2h
/
E . E i I p E C 1.24 l f i.23 w [ I. 1.22 I 1.2 I I - t t t t t I f i f f I I 1 i i t
- I I t t i i 1 if i f f I t I l 1 i ! i1 f f O 00 0.1 0.2 0.3 0.4 0.h 0.6 0.7 0.8 0.9 1 00 TAU I
FIGURE 4-3 I _.
-14
- ._ .-}}