ML20092F004
ML20092F004 | |
Person / Time | |
---|---|
Site: | Catawba |
Issue date: | 11/22/1991 |
From: | Clark R, St Clair R DUKE POWER CO. |
To: | |
Shared Package | |
ML20092F000 | List: |
References | |
CNEI-0400-14, CNEI-0400-14-R00, CNEI-400-14, CNEI-400-14-R, NUDOCS 9202190043 | |
Download: ML20092F004 (18) | |
Text
. .- -- - - - _ - _ - . - _ _ - . - . - - . -- _ _____ -_-. . . _ --
' CNEl&OO14
' Page I of l$
Rev.000 s
9 Catawba Nuclear Station COLR 1 '
f~ aco/4 FEB 5 m Catawba Unit 2 Cycle 5 CONTettgy N t AR $1 Core Operating Limits Report t
Noyemher 22,1991 Duke Power Company {
Prepared by: YAdf M. /*La Checked by: 'Ad'L dM4C v Approved by: [ 74 M CONDITION o -
9202190043 920207 PDR ADOCK 05000414 P PDR f
CNEleMX) 14 Page 2 of 15 Rev.000 Catawha 2 Cycle 5 Core Operating Limits Heport REVISION LOG Revision Effective Date Effective Paces Originalissue 22 November 1991 Pages 1 15
(
4
I
. CNEl.040014 )
Page 3 of 15 I
Rev.000
- Catawba 2 Cycle 5 Core Operating Limits Report I
1.0 Pure Onarniine I Imits Renart !
This Core Operating Limits Report. (COLR). for Catawba Unit 2. Cycle 5 has
.. been prepared in accordance with the requirements of Technical Specifleation 6.9.1.9.
The Technical Tec03.Ur 44 i by this report are listed below:
3/4.1.1.3 Moderan4 . sinperature CNfficient 3/4.1.3.5 Shutdown R viinsenion Limit 3/4.1.3.6 Control Rod i.nenien Linut 3/4.2.1 Axial Flux Difference
-3/4.2.2 Heat Flux Hot Channel Factor ;
3/4.2.3 Reactor Coolant System Flow Rate and j Nuclear Enthalpy Rise Hot Channel Factor . .;
i j
i l
l i
e h
p
CNEl600 i6 i Page 4 of 15
- Rev.000 i ,
Catawba 2 Cycle 5 Cure Operating Limits Heport
}
}
i 2.0 Onerniinr' I imits I
De cycle specific parameter limits for the specifications listed in section 1.0 are presented in the following subsections. These limits have been developed using NRC approved methmlologies specified in Technical Speelfication 6.9.1.9.
! 2.1 Modernene Temnerneure (%,tricient #Rn.cirtention 3/11.1.3)
- 2.1.1 ne Moderator Temperature Coefficient (MTC) Limits are
- ,
The MTC shall be less positive than the limits shown in Figure 1. The ,
BOC/ARO/lizP MTC shall be less positive that 0.7
- 104 AK/KrF.
The EOC/ARO/RTP MTC shall be less negative that .4.1
- 104 AK/KtF.
t 2.1.2 ne MTC Surveillance Limit is:
The 300 PPM /ARO/RTP MTC should be less negative than or equal to 3.2
- 104 AK/KrF.
Where: BOC stands for Beginning of Cycle ARO stands for All Rods Out ilZP stands for llot Zero (Dermal) Power EOC stands for End of Cyc!c RTP stands for Rated Thennal Power 1
i
)
-- ' -. ,w-, , .% .-..-,--.-,-4.%- -
.--.,------.-.m-r .
, c-r- -
.--.r. , v ,- wr'~,, ,e,- -- - e + -
CNEl4M(014 Page 5 of 15 Rev.OC0 Catawba 2 Cycle 5 Core Operating Llanits Report I
C 0.9 --
y 0.8 -
Unacceptable Operation 9
g 0.7
=.
50.6- -
Acceptable Operation 0.5 --
0.4 --
i.
w 30.3- -
5 0 .2 --
G 2
= 0.1 -
0 l . l l l l l l l 0 10 20 30 40 50 60 70 80 90 100 Percent of Rated Thermal Power Figure i Moderator Temperature Coefficient Versus Power Level
CNE!4M(X) 14 Page 6 of 15 Rev. 0CX)
Catawba 2 Cycle 5 Core Operating Limits Report i
i j
2.2 Rhuf rinwn Hud inwrtlan I lenit (Rnwinention 3/4.1.3.5) 2.2.1 The shutdown nxis shall be withdrawn to at least 226 steps.
l l
2.3 Control Rod Inwetion i Irnits (Snecinension 3/4.1.3_6) 2.3.1 The control rod banks shall be limited in physical insenion as shown in Figure 2.
2.4 Avini Flur DINerence (Roccificnelan 3/4.2.1) 2.4.1 The AXIAL FLUX DIFFERENCE (AFD) Limits are provided in Figure 3.~
2.4.2 The tarSet band during base load operation is not applicable for ,
Catawba 2 Cycle 5.
2.4.3 1he minimum allowable power level for Base Load Operation (APLW) is not applicable for Catawba 2 Cycle 5.
4 CNEl.040014 Page 7 of 15 Rev.000 Cataw ba 2 Cycle 5 Core Operating Limits Report 1
Fully Witherawn
\
(27.4 %,226) (TI.8%,228) ;
220
~ '
200 BANK B ,
1
~
ISO .
(0%,163) (100%,181) c O 140
] DANK C E 120 E l 2 l
$ 100 l
8 l
=
E 80 S BANKD a
E 60 e
li* -
(0%,47) 40 20 (MO) Fully inserted ki i I I I i I I O 60 50 100 O 20 40 Relative Power (Percent)
Figure 2 Control R(xl Bank Insertion Limits Versus Percent Rated Thermal Power
l CNEl.04(S14 .
Page 8 of i$
Rev 000 4
3 Catawba 2 Cycle 5 Core Operating Limits Report 120 .
I 110 ,
(.an.lom (+ 10.100)
- l } l 1g
, , (tInaccepietde Orwentian/ \
I
/ \ t !-- - "- opereuen ,
1- / \\
70 [ +
J %% \
- / \
~
f )
y (* MM / L (+28.$0)
,10 i
-20 10 n ,
50 4 30 20 40 0 10 - 20 30 40 SO Anhi Fles Differvaev(4 Onee il 4
Figure 3 Percent of Rated Hermal Power Versus Axial Flux Difference Limits 1
.I._..
' l ctret.040014 :
Page 9 of 15 l Rev. (X)0 Catawba 2 Cycle 5 Core Operating Limits Report j l
l l
l 2.5 llent Nr llot Channel Factnr . F (Z) Q (Specification 3/4.2.2)
F9 (Z) s. F"" o
- K(Z) for P > 0.5 1
P L Fn (Z) s F"" o
- K(Z) for P s 0.5 0.5 Thermal Power Rated Thermal Power 2J.1 F"" = 2.32 0
2.5.2 KfZ)is provided in Figure 4.
I 2.5.3 W(Z) values are provided in Figures 5 through 7. .
2.5.4 Dase load W(Z)'s are not applicable for Catawba 2 Cycle 5.
r T
b y... .I_.,-.r.n3-n.,y-- ,e .
,-.--.- . e m.h. , , , . . -
,,..,y ,,,-..,%c-~
, o yo...,, ~ , , . . , .. .y or ,, r-.----E.r...-e-,..4-w,
f i CNEI4W1014 Page 10 of 15 Rev.000 i t
i I
b Catawha 2 Cycle 5 Core Operating Limits Report i
i 1.2 i.
(0.0,1.00) (6.0.1.00) i 0.8 -
@0.6 -
(12.0.0.647) 0.4 -
r 0.2 -
P 0
O 1- 2 3 4 5- 6 7 8 9 10 11 12 Core Height (ft)
Figure 4 i K(Z), Normalized FQ(Z) as a Function of Core Height ;
i 4
4 4
L f
_____.____________________.____..__m____ .___________._.___._________m.__ m . . _ _ _ . _ _ . . _ _ _ _ . . _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ . _ _ _ _ . . _ _ _ _ _ _ _ . _ _ _ _ _ _ _ _ _ _ _
4 CNEl 04(014 Page !! of 15
- Rev.000 Catawba 2 Cycle 5 Core Opirating Limits Report KI!CRT 301, (ITIfl w(El 1,55 , , , , , , , ,
, ,
- 0.00 1.0000
, , , , , , 4 , 1 i , ' O.20 1.0000
' '
- 0.40 1.0000
!
- 0.60 1.0000
' ' ' 8 ' ' ' ' ' ' O.80 1.0000
' ' ' ' ' i ' ' ' 1.00 1.0000 1*EO * ' t * ' ' ' ' ' 1.20 1.0000 e i
- e ' ' 1.40 1.0000
. . ia i e i
- 1.60 1.0000
, g i , 6 1.80 1.4716
, , , 4 4 e 2.00 1.4533 1.45 2.20 1.4283
' ' ' ' ' ' 2.40 1.4026
' ' i ' ' ' 2.60 1.3166
' ' "' ' 2.00 1.3519 i ' ' 3.00 1.2318
' 4 l
- 3.20 1.3169 1*# . . i # 3.40 1.3055
. . , , 3.60 1.2925
. . 4 i e 3.30 1.2716
, , , i i 4.00 1.2630
, , , , ,, , , 4.20 1.2496 1.35 , , , , , , 4.40 1.2359 4.60 1.2205 I ' I ' ' ' 4.80 1.203" I ' ' ' 5.00 1.;*
- 6 ' ' 5.20 ;
6 i
- 6 S.40 1 30 . . , t n 3.50 1.
, i t 4 S.80 1.1. .
N , i e a 6.00 1.1325
, , ; 6.20 1.1432
{ ;
6.40 1.1530
, , 4 4 1.25 , , , , , - 6.80 1.1617 6.80 1.1690 -
' '
- 1.00 1.1147
' ' i- 7.20 1.1787
- i F 7.40 1.1804, a ' i e a' 7.60 1.1796 1 20 . . i
- i , 7.80 1.1781
. . 6 i i a c 8.00 1.1775
. e a 6 n- ~oa.- a .- 8.20 1.1747
, , , ^ ^
- I.40 1.1723 8.60 1.1694
' ' ' ' ' " 8.80 1.1631:
1.15 ' ' ' ' ' '
A- 9.00 1.1565
' ' ' I
- 9.20 1.1550
' ' ' ! ' 9.40 1.1641'
' ' ' 6 I I t.60 1.1734'
' i i e i I 9.80 1.1781 1.10 , , , , 10.00 1.184e-
. , e i i 10.20 1.1909
, , , , ,
- 10.40 1.000C
, , , , , , , , ; , , ' 10.60 1.000C
- 10.80 1.000C 1.05 '
' 11.00 1.000C-
' ' ' ' ' ' ' ' ' 11.20 1.000C-
' ' ' ' ' ' ' i
- 11.40 1.000C
' ' ' ' _8 6 ' i I
- 11.60 1.000C i i i e *
- i 4 i
- 11.30 1.000C-i . .
- i i e i 6 i
- 12.00 1.000C 0 2 4 6 8 10 12 bott :a CCPI HEIGHT (TE3lT) top Figure 5 Catawba Unit 2 Cycle 5 RAOC W(Z) at 150 MWD /MTU Top and Bottom 15% excluded as per Tech. Spec. 4.2.2.2.0
CNEl.0440-l4 Page 12 of 15 Rev. (Xf)
. Catawba 2 Cycle 5 Core Operating Limits Report m2caf sn.
(FEST) W(El
' O.00 1.0000 l 1.s5 ' ' ' ' , , , , , ,
' O.20 1.0000 -
' ' ' O.40 1.0000 l
' ' i I i
- 0.60 1.0000 i 6
- 0.80 1.0000 ,
t e
' 1.00 1.0000 1.80 e 1.20 1.0000
' 1.40 1.0000
' 1.60 1.0000 1.80 1.2144 2.00 1.2731 1,43 2.20 1.2624 2.40 1.2312 2.60 1 2396 2.00 1.2274 3.00 1.2139 3.20 1.2097 1.40 3.40 1 2114 3.60 1.2111 3.00 1.2193 4.00 -1.2209 4.20 1.2207 1,3 4.40 1.2108 4.60 1.2150 4.80 1.2091 S.00 1.2022 S.20 1.1?
i.20 i:::
.. 0 1-1
, 1..
me 6.00 ..
~ 6.20 1.201C 3 ^ 6.40 1.2112
- 6.60 1.222t 1.25 a- ^ 6.80 1.2301
~ ^
^^4 '
7.00 1.23Bi
- a- " .n" 7.20 1.2448 n- X -E e "-
1.40 1.2483
-- = a 7.60 1.2494 1.20 a d . 1.00 1.2488 a ,a 8.00 1.2441 8.20 1.238' O.40 1.227!
B.60 1.218' s.s0 1.220! t 1.15 9.00 1.224!
9.20 1.22O(
9.40 1.2321 -
9.50 1.23 4 t 9.80 1.233*
1.10 10.00 1.23s' 10.20 1.241'
' 10.40 1.000
- 10.60 1.000
? 10.80 1.000 1.0g
- 11.00- 1.000
' ' ' ' 11.20 1.000 8 *11.40- 1.000 e
- 11.60 1.000 i e e ' 11.00 1.000
. . . i i ' 6 i 4 ' 12.00 1.000 0 2 4 5 4 10 12 botton CORE 1EIGitT (TEET) top Figure 6 Catawba Unit 2 Cycle $
RAOC.W(Z) at 8000 MWD /MTU Top and Bottom 15% excludal as per Tech. Spec. , 0.2.2.0
CNE!41(nl4 Page 13 of 15 Rev.000
- Cat. wha 2 Cycle 5 Core Operating Limits Heport HEICHT ECL (TIET) Witi I'gg ' ' ' ' ' '
- 0.00 1.000 i !
i '
' O.20 1.000 i e i i * ' O.40 1.000
, , 4 i
- 0.60 1.000 4 6 6 a ' O.80 1.000
, i i i i ' 1.00 1.000 1.50 , .
- 1.20 1.000
' i ' 1.40 1.000
' 1.60 1.000 1.80 1.271 2.00 1.264 1.45 2.20 1.258 3.40 1.25t 2.60 1.243 2.80 1.231 3.00 1.22' i , 3.20 1. 21*.
1.40 3.40 1.22:
3.50 1.234 3.80 1.241 4.00 1.23:
4.20 1.23t 1.35 i '
4.40 1.25' t 4.60 1.21' i 4.80 1823+
S.00 1.24!
S.20 1.24 5.40 1.248 1.30 s.60 1.24.
3.00 L**
$ 4
^# E, a <>
6.40
= .*"*a i s.60 1...
1.25 --, a "a. ,
6.80 1.27 a 4 7.00 1.27 a m 6 7.20 1.27 a a **... i 7.40 1.27 1.60 1.27 7.80 1.25 8.00 1.25 8.20 1.24 8.40 1.23
' 8.50 1.22
' 8.80 1.21 1.15 ,
9.00 1.21 9.20 1.21 9.40 1.21 i 9.50 1.21 9.80 1.21 1.10 , 10.00 1.21 10.20 1.21
- 10.40 1.0t
- 10.60 1.DC 6 ' 10.80 1.0t
- 11.00 1.0t 1.05 i i e i e ,
- 11.20 1.ct i i e
- 11.40 1.Dt
' 11.60 1.0L
- 11.80 1.0t
' ' ' 12.00 1.0t 1.00 0 2 4 6 8 10 12 botton CORE IEIGHT (FTI:7) top Figure 7 Catawba Unit 2 Cycle 5 RAOC W(Z) at 13000 MWD /MTU Top and Bottom 15% excluded as per Tech Spec. 4.2.2.2.0
CNEl.040014 Page 14 of 15 Rev.000 Catawba 2 Cycle 5 Core Opeting Limits Report
! l t
i 2.6 R('E Nw Rule and Nuclear Enthninv Rise Had ('hrnnel Fncinr . FNAH ,
(Speci0 cation N4.2.3) l.
I FNan R=
FRTP4H * (1 + MFAH * (1.P)) [
s a
Thermal Power where: P= =
Rated Thermal Power ;
2.6.1 FRTP4H " 1449 2.6.2 MFAH = 0.3 2.6.3 The Acceptable Operation Region from the combination of Reactor ,
Coolant System total flow and R is provided in Figure 8. l r
I h
I
_ . _ . . , . . _ - . , , _ _ - - . - . . - . ... - .. .. _ a _ . - . . _ . _ . . - . ~ .- ._ . . _ . . .. .-
= - - . _ - - . - _ _ _ - _ _ . _ _ . . - .- - _-_ _ _ .._- __. - . -. .__ - -. - --
i CNEI.040014 Page 13 of 15 Rev. (V4 Catawba 2 Cycle 5 Core Operating Limits Report Penalties of 0.1% for undetected feed ana 4.0% for incere rneasurementare of Fgator venturl fouling and rnessurement uncertainties of incluM in We Nure.
3g 40.0 :
39.5 - Permiselble p,,gggg,g . <
OPerntlan Region op,,gg,,
g,yg,, ,
g 39.0 - -
@ (1.000. 38.780)
Restrteted Operation Region (Power f,90% RTP) 38.5 - ,
5 (0.994, 34.372) g Reetncted Operation Region (Power 198% RTP)
E 38.0- *
(0.988. 37.985)
, Reetncted Operation Region (Power 194% RTP) ,
(0.982. 37.597) d 37.5 - -
3 Restncted Operavon Regen (Power <92% RTP)
(0.977. 37.210) 37.0 - Restncted Operanon Regen (Power 190% RTP) -
g (0.971, 38.822) i 38.5- -
36.0 , , , , , , , ,
0.93 0.94 0.95 0.96 0.97 0.98 0.99 1.00 1.01 1.02 R. FOUR LOOPS IN OPERATION I
Figure 8 RCS Flow vs. R Four Loops in Operation )
)
7 DOCUMENT CONTROL Nn cNer-0400-1s O
. REVISION NO.
PAGE NO, 1 ar 3 ,
)
TITLE *. CATAWBA 2 CYCLE 5 SNACORE Theorectical Factors !
SIGN OFF DATE PREPARED BY du $ 4 _
/thq/4r
( -
I CllECKED BY M b [ 4fd v /t /[4 [c; /
(
APPROVED BY /Mhk ' t '
lM hA 00NDm0N 1.
1 DMLdf#
REHSED BTihld-1 SSC S P /;.g I l JM 6 '1992 Lhtk$#
9
,,,4- 3-. ,,-,--,m . . . . s.,,,-s_s - ,. _,__,, , , ,y ., _ jw. y _,-.--,_y,,- w., ws, ,3 ..,,y- ., y,,,
_.m.________.__._ _ - _ . _ _ - _ . . _ _ . . _ . . _ . _ _ _ . . . . . _ . _ _ _ _ _ _ _ _ _ . _ .
- I I
CNE! 040015 '
Page 2
, -l l
.- i 6
i l ;
December 18,1991 -
t
- 0. P. florne, Reactor Engineer Catawba Nuclear Station ;
Subject:
Catawba 2 Cycle 5 SNACORE Theoretical Factors The C2C5 Theoret.ical Factors have been generated and stored in VAX acaunt CAT:: PROD $8ND. The l
- filenames and their respective burnup ranges are listed in the attachment. The factors have received an i*
engineering review within Nuclear Design as documented in calculation file CNC 1553.05 00 0134. A
, copy of this calculation file will be sent to 0. P. Horne, j Please contact me at 3821667 If you have any problems or questions.
/
N 4 . l S. L. Abbey, Anociate Engineer
+
Nuclear Engineering - -
Nuclear Services - i r
6 cc: K. S. Canady -
R. H. Clark
- R. R. St. Clair M. L. Elder _
t 6
.I i
a Y
= .
[
6
CNEl 040015 Attaciument '
C2005 Theoretical Factor Files M ooretloal Esposure Nuamber of Factor File Hans, Assentblames SNDUl!ZP.DAT BOC 482 SNDU30P.DAT BOC _ , ,
482 SNDU150.DAT BOC 325 519 SNDU500.DAT 326 750 519 SNDU1KDAT 751 1500 519 SNDU2KDAT 1501 2500 576 SNDU3KDAT 2501 3500 576 SNDU4KDAT 3501 4500 576 SNDU5KDAT 4501 5500 605 SNDU6KDAT 5501 6500 605 SNDU7K.DAT 6501 7500 605 SNDU8KDAT 7501 8500 605 SNDU9KDAT 8501 9500 599 SNDU10KDAT 9501 10500 599 SNDU11KDAT 10501 11500 599 SNDU12KDAT 11501 12500 599 SNDU13K.DAT 12501 13500 561 SNDU14K.DAT 13501 14500 561 SNDU15K.DAT 14501 15500 561 SNDU16K.DAT 15501 16700 561 Note: All Theoretical Factors sets contain two axial configurations. Sets SNADUHZP.DAT and SNADU30P.DAT are for approximately 0% RTP and 30% RTP conditions, respectively.-
.