ML20044F580
| ML20044F580 | |
| Person / Time | |
|---|---|
| Site: | Hatch  |
| Issue date: | 05/31/1993 |
| From: | GEORGIA POWER CO. |
| To: | |
| Shared Package | |
| ML20044F579 | List: |
| References | |
| NUDOCS 9305280275 | |
| Download: ML20044F580 (20) | |
Text
r EDWIN I. HATCH NUCLEAR PLANT UNIT 1 CORE OPERATING LIMITS REPORT for FUEL CYCLE 15 Revision 1 May 1993 7BP2288M Zi888a21
- - - _ _ - _-- _ S
interoffice Corresoondence
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GeorgiaPower AE
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DATE: May 12,1993 RE: Hatch Proiect Support - Licensine Core Operating Limits Report for Hatch I Cycle 15 Revision 1 File: Fuel Cycle Technical leg: HL-3300
' .i&e FROM: S. J. Bethay e~
] 4-TO: ALL UNIT 1 TECHNICAL SPECIFICATIONS MANUAL HOLDERS By amendment 168 to the Unit 1 Technical Specifications, the NRC authorized relocation of cenain fuel-related limits from the Technical Specifications to the adjunct Core Operating Limits Repon (COLR). This letter transmits to all Unit 1 Technical Specifications manual holders a copy of Revision 1 of the COLR for Hatch 1 Cycle 15. This document should be utilized in conjunction with the Unit 1 Technical Specifications, as referred to in the Specifications. Normally, the shift technical advisor or reactor engineer will use this report.
Where necessary, the fuel limits from the COLR are included in plant procedures.
Please discard Revision 0 of the COLR for Hatch 1 Cycle 15, which was issued May 6, 1993, since it is no longer applicable. If you have questions regarding Revision 1 of the Unit 1 COLR for Cycle 15,please contact me at extension 8-821-7392 or telephone number (205) 877-7392.
SRP/sp colrwp Enclosure cc: NORMS em
GEORGIA POWER COMPANY EDWIN I. HATCH NUCLEAR PLANT UNIT 1 FUEL CYCLE 15 CORE OPERATING LIMITS REPORT REVISION 1 Southern Nuclear Operating Company Post Office Box 1295 Birmingham, Alabama 35201
I i
EDWIN I. HATCH NUCLEAR PLANT !
UNIT 1 FUEL CYCLE 15- !
CORE OPERATING LIMITS REPORT l
li TABLE OF CONTENTS !
P.AEC. l 1.0 Introduction 1- l 2.0 Limiting Control Rod Pattern 1 f 3.0 APLHGR Limit 2 l 4.0 MCPR Limit 11 4.1 Two Recirculation Loop Operation 11 i 4.2 Single Recirculation Loop Operation 11 -
5.0 LHGR Limit 15 ,
6.0 References 15 !
F i
I
.1
'i r
wp51colr15 i May 1993
i EDWIN I. HATCH NUCLEAR PLAhT I UNIT 1 RJEL CYCLE 15 l CORE OPERATING LIMITS REPORT !
TABLE OF CONTENTS (Continued) !
t
+
LIST OF FIGURES ,
EREC-3-1 MAPFAC y 3 I t
3-2 MAPFAC , 4 ,
3-3 APLHGR Rate Limit vs Average Planar Exposure I (BP8DRB284H) 5 l 3-4 APLHGR Rate Limit vs Average Planar Exposure !
(BD296A) 6 P'
3-5 APLHGR Rate Limit vs Average Planar Exposure
' f (GE9B-P8DWB315-8G4.0-80M-150) 7 3-6 APLHGR Rate Limit vs Average Planar Exposure !
- (GE9B-P8DWB314-8G4.0-80M-150-T) 8-3-7 APLHGR Rate Limit vs Average Planar Exposure .
(GE9B-P8DWB331-10GZ-80M-150-T) 9 3-8 APLHGR Rate Limit vs Average Planar Exposure ,
(GE13-LUA - GE13-P9HTB327-12GZ-100M-146-T) 10
.l t
4-1 Power-Dependent MCPR Multiplier (K,) 12 s r
i 4-2 Flow-Dependent MCPR Limits, MCPR(F) 13 ;
i 4-3 MCPR Limit as Function of Average Scram Time j and Fuel Type 14 !
S 9
I wp51colr15 ii May 1993 !
t
l l
EDWIN L HATCH NUCLEAR PLANT !
UNIT 1 FUEL CYCLE 15 i CORE OPERATING LIMITS REPORT i
I
1.0 INTRODUCTION
j i
The Core Operating Limits Report (COLR) for Plant Hatch Unit I Cycle 15 is prepared in accordance with the requirements of Technical Specification 6.9.1.11. ;
The core operating limits presented herein were developed using NRC-approved i methods (References 1 and 2). Results from the reload analyses for the General :
Electric (GE) fuel in Unit 1 Cycle 15 are documented in References 3 and 4. !
i The following cycle-specific core operating limits are included in this report:
l
- a. Operation with a Limiting Control Rod Pattern (for a Rod t Withdrawal Error (RWE)) -Technical Specification 3.3.F. '
- b. Average Planar Linear Heat Generation Rate (APLHGR)'-
f Technical Specification 3.11.A.
- c. Minimum Critical Power Ratio (MCPR) - Technical Specifications 3.11.Cand 4.11.C.
i
- d. Linear Heat Generation Rate (LHGR) - Technical Specification l 3.11.B.
I .
- 2.0 LIMITING CONTROLROD PATTERN (Technical Specification 3.3.F) 2 Both Rod Block Monitor (RBM) channels shall be operable as specified in
- Technical Specification 3.3.Fand when: l l
4
- a. THERMAL POWER is < 90% of RATED THERMAL POWER :
and the MCPR is < 1.70,or l i
- b. THERMAL POWER is >_90% of RATED THERMAL POWER i and the MCPR is < l.40. !
1 wp51colrl5 1 May 1993 t
Plant Hatch Unit 1 RDel Cycle 15 Core Operating Limits Report 3.0 APLHGR LIMIT (Technical Specification 3.11.A)-
The APLHGR limit is given by the applicable rated-power, rated-flow limit taken from Figures 3-3 through 3-8, raultiplied by the smaller of either: j
- a. The factor given by Figure 3-1,or j t
- b. The factor given by Figure 3-2.
j For the fuel types whose APLHGR limits are shown in Figures 3-3 through 3-8, the APLHGR limit shall be applied to each axial location in the fuel assembly.
As required by GESTAR Amendment 19, the hand-calculated APLHGR values for a multi-lattice (i.e.,GE8-296, GE9-331, and GE13-LUA) fuel must be less than or equal to the APLHGR limits shown in Figures 3-4,3-7, and 8, -
respectively. When APLHGR values are determined by the process computer,.
the lattice-dependent APLHGR , limits are used. Under these conditions, some ;
axial locations may have APLHGR values exceeding the values shown in Figures 3-4,3-7, and 3-8.
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MAPLHGRSTO = STANDARD MAPLHGR LIMITS g FOR 25% > P: NO THERMAL LIMIT 5 MONITORING REQUIRED z NO LlMiis SPECIFIE D A g (sa.47Ull
' 4 50% COME FLOW
$ FOR 25% 4 P < 305:
g (SL41ull MAPFACp = 0 686 + 0 006224 le-30%)
eS ,
FOR < 80% CORE F LOW MAPF ACp = 0.433 + 0 006224 (P-30%)
FOR > 90% CORE F LOW 1 > 50% CORE F LOW FOR 30% < P MAPF ACp = 10 + 0 006224 fr-100%)
06 -
l FOR 52%#. (SLO) RAAPF4 = (L75 I ?
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.. e( i i i i i i i i i i i e i g 20 a 20 to 50 en m eO s0 300 g POWER lE ****di G
B FIGURE 3-2 MAPFAC,
l Pl:nt H tch Unit 1 Fe:I Cycle 15 Core Operating Limits Report l
L 2d +
1 i 1' 1. .. 2 a
UNA;CCEPTABLE!
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l 8.0 111 !
9 10.0 12.3 ,
, i 12.5 12.4 FUEL TYPEi BP8DRB284H
' 8.5 I
[ t ! 80 - MIL CHANNELS ,
84 .. . . .i,,,,,..........i ..>i.a 0 5 10 15 20 25 30 35 40 45 AVERACE PLANAR EXPOSURE (GW.Vst)
FIGURE 3-3 AVERAGE PLANAR LINFAR HEAT GENERATION RATE LIMIT '
vs. AVERAGE PLANAR EXPOSURE >
wp51colr15 5 May 1993
l Pirnt Httch Unit 1 Fu:1 Cycle 15 Core Operating Limits Report
' I
- 13
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UNACCEPTABLE
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4.0 12.08 12.73
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! OPERATION i 8.0 , %
2 10.0 12.81 [
6--- FUEL TYPE: bD296A
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80 MIL CIIANNELS E ! ! 5.36 0
- 5. ....... . . .... . , ,,. .. . i.. .. .e .4 .
0 5 10 15 20 25 30 35 40 45 50 AVERAGE PLANAR EXPOSURE (GWOO
'NOTEI THIS IS THE APLHGR LIMIT FOR THE MOST UMmHG LATTICE AS A FUNCTION OF AYERAGE PLANAR EXPOSURE.
f FIGURE 3-4 AVERAGE PLANAR LINEAR HEAT GENERATION RATE LIMIT vs AVERAGE PLANAR EXPOSURE wp51colr15 6 May 1993
Pl:nt Hatch Unit 1 Fuel Cycle 15 Core Operating Limits Report l
l l
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- l! 1 P ' 13 2' UNACCEPTABLE!
u7 \ LD.PERATION!
l 11.79 0
11 COURDINNTES l X Y !
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0.2 11.92 i f l 3 1.0 12.03 I j
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- 4.0 12.56 5.0 12.75 ACCEPTABLE 6.0 12.96 7.0 u.15 2
7-- 8.0 13.24 OPERATION , .
9.0 13.31 2 10.0 13.4 1 l
g NN i
6-- 12.5 13.50 E 5.86 GE98 P8DWB3154G4.040M.150 5
..,, 4 ... ...
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.. 4 at51.6 GWd/st 4 i i. .
AVERACE PIANAR EXPOSURE (GWe'st) l FIGURE 3-5 AVERAGE PLANAR LINEAR HEAT GENERATION RATE LIMIT vs l AVERAGE PLANAR EXPOSURE wp51colr15 7 May 1993
Plant Httch Unit 1 Fuel Cycle 15 Core Operating Limits Report !
13 g
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............ .........:4
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12 7 OPERATION! ,
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,,, 10-0.0 11.83 g -
3 0.2 11.90
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2A 12.17 g O -
3A 12.34 8.98 l 5 -
4.0 22.s.
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74 13. 2 7-- EA 13.22 OPERATION i
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- 10A 13.40 NN y
- 6-- 12.5 13.50 g q , ;
GE9BPSDWB3144G4 A-80M-150-T st 51.87
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5 .. . . .. .... ... ........ ..., ... . ....
AVERAGE PLANAR EXPOSURE (GWd/st) l FIGURE 3-6 l
1 AVERAGE PLANAR LINEAR HEAT GENERATION RATE LIMIT vs. AVERA.GE PLANAR EXPOSURE wp51colrl5 8 May 1993 l
h Plant Hetch Unit 1 Fuel Cycle 15 '
Core Operating Limits Report ,
1 h
7 A_ 12ss '
- li !
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(i 12.15 :
ji 73
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3.0 1117 .
~3 : 40 12.41 !
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SA lus 6.0 1190 ACCEPTABLE !
7.0 13.07 7-- 8A 13.22 OPERATION :
- 9.0 13J2 !
- 10A 13.25 .
6-- 115 13.13 FUELTYPE:
SAS -
- GE98.P8DWB331 10GZ.80M-156.T at 50.06}k G W d/st 5
, , \ '
. . . . . . .i... .i.. . ,. ... i. . . i +
O 5 10 15 20 25 30 35 40 45 50 AVERAGE PIANAR EXPOSURE (GWd/st) l
(
l NOTL APLHGR UMIT FOR MOST UMmNG
- LATTICE AS FUNCTION OF AVERAGE i elmAR mE.
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FIGURE 3-7 '
AVERAGE PLANAR LINEAR HEAT GENERATION RATE LIMIT vs. AVERAGE PLANAR EXPOSURE wp51colr15 9 May 1993
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Plant Hetch Unit 1 Ftrl Cycle 15 Core Operating Limits Report l NICCEPT ELN! ,
12
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"'Y OPERATION! i E IDW EXPOSURE
-g 11_~ COORDINATES 10.861 6 - X Y b
0.0 11.07 2 3,:_ _ 0.2 11.14 10.19 h,__ N 11N ' 5' 3.0 c _
4.0 11.70 8.90 i l
- _ 11.70 !
J 5.0 11.70
% 5:_ 1: li:'a ACCEPTABLE 8.0 11.70 7 l 7f
. , :g jjj OPERATION 6.88 i i:. ,
6.51 hT 6 FUELTYPE: GE13LUA $7.27 N I
GE13.P9HTE32712CZ.100M.146.T 5 i. ., i ,, i.,i,,,, ,,,,,li,,,!,,,,,',,,,!,,,, ,,,, ,,,, , , ;
0 5 10 15 20 25 30 35 40 45 50 55 t AVERAGE PIANAR EXPOSURE (GWd/st) 6
' NOTE: .
APLHGR UMIT FOR MOST UMITING ;
IATT1CE AS FUNCTION OF AYERAGE PLANAR EXPOSURE, i
FIGURE 3-8 l 1
i AVERAGE PLANAR LINEAR l HEAT GENERATION RATE LIMIT !
i ys. AVERAGE PLANAR EXPOSURE !
wp51colr15 10 May 1993 ;
i d
.-, m,- -- -
Plant Httch Unit 1 Full Cycle 15 '
Core Operating Lhnits Report j
4.0 MCPR LIMIT (Technical Specifications 3.11.Cand 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. Note that in Figure 4-3, the rated-power and rated flow OLMCPR is fuel-type -;
dependent; e.g.,the Option B limits are 1.25 for GE7 and GE8 fuel,1.26 for GE9 i fuel, and 1.41 for GE13 fuel.
4.1 Two Recirculation Imop Ooeration t
For 25% .s;_ power < 30%, the OLMCPR is given in Figure 4-1. For power 130%, the OLMCPR is the greater of either: j
- a. The applicable limit determined from Figure 4-2,or .!
- b. The appropriate K,given in Figure 4-1, multiplied by the ,
appropriate , limit from Figure 4-3 where the scram time l dependence is given in Technical Specification 4.11.C.2.
{
f 4.2 Sinele Recirculation loco Operation !
For single-loop operation, the MCPR operating limit shall be 0.01 greater !
than the two-loop value which is determined' as specified in Section 4.1. j I
i i
wp51colrl5 11 May 1993 i i
f
>50% FLOW 7 6pERATING LIMIT MCPR(P) = Kp i PEW TING LIMIT MCPR(100)
Ci g 2.4-i i----
k FOR P < 25% : NO THERMAL LIMITS MONITORING REQUIRED NO LIMITS SPECIFIED hg gg .. j FOH 25% < P < P ==. (WHERE:P ==. = 30% FOR HNP -1,2) "{g
$ A'2.3 ! Kp = (K + 0.02(30% - P))/OLMCPR(100) E.
V Q-a tr 2.2_
AND K = 2.00 FOR $_50% CORE FLOW h
m V u. .
. 50% FLOW K,= 2.40 FOR > 50% CORE FLOW =E.
tP g 2.1 - FOR 30% 5 P < 45% : -@ Q
$w -
l Kp = 1.28 + 0.0134 (45%-P) $ O.
N $ 2.0- ----I------
FOR 45% $ P < 60% : -
O -l t Kp = 1.15 + 0.00867 (60% - P)
- ' ' FOR 60% < P :
M& F 1.5 i Kp = 1.0 + 0.00375 (100%-P) bd -
! ! M M g :s 1.4 - l --t:
u a0 - : \
l OW 3,3 j j I
i : i N l ! ! N
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l I I-i :N j ! ! N : } N
- %YPASS2 i : N N_
1.0 - i i i i i i i i , i 20 25 30 40 50 60 70 80 90 100 POWER (% RATED) v w
@ FIGURE 4-1 POWER-DEPENDENT MCPR MULTIPLIER (Kp)
PI:nt H tch Uzit 1 Fu:1 Cycle 15 Core Operating Limits R: port l
I 1.7 3
~
~
hiAXIMUM FLOW RATE =
, FOR We (% RATED CORE FLOW) 2: 40%
j 117 % MCPR(F)= MAX (1.20, AfWe/100+Bf) g 112 % ~
107% .
MAX FLOW Af Bf 102.5 % 117.0 -0.632 1.809 i 112.0 -0.602 1.747 1.5 f!'h i 107.0 -0.586 1.697 b
\ ![ 102.5 -0.571 1.655
/.
/ '
1.4 ! _
4 l ; ,
i j
l :
_ j
' I 1.3
- \l !
- \
1.2 FOR We (% RATED CORE FLOW) < 40%
_ P1CPR(F)=(AfWc/100+ Bf)
_ *[1+0.0032(40.Wc)] ,
l l 1.1 , , , . i ,,., , , . ,,,,,,.,, . . . . . , i ;
30 40 50 60 70 80 90 100 110 120i CORE FLOW (% rated)
FIGURE 4-2 FLOW-DEPENDENT MCPR LIMITS, MCPR(F) wp51colr15 13 May 1993
~
)
Plant H:tch Unit 1 Full Cycle 15 Core Operating Limits Report 1.42 l l l l l l l l I
1.40 GE13 LUA c 138 M 136 Es2 N
O 134
- a. .I t C ! f i
132 f
< i M I p 130
< /
$ 1.28 GE9B l 3 ! I GE7B GE8B 1.24 !
. 1.22 O.0 0.1 0.2 03 0.4 0.5 0.6 0.7 0.8 0.9 1.0 TAU .
t FIGURE 4-3 MCPR LIMIT AS FUNCTION OF AVERAGE SCRAM TIME ;
AND FUEL TYPE :
i I
wp51colr15 14 May 1993
Plant Hrtch Unit 1 Fuel Cycle 15 Core Operating Limits Report j 5.0 LHGR LIMIT (Technical Specification 3.11.B)
The LHGR limit is 13.4 kW/ft for all GE7 fuel. The LHGR limit for GES, GE9, {
and GE13 fuel is 14.4 kW/ft. -!
t k
6.0 REFERENCES
i t
- 1. " General Electric Standard Application for Reactor Fuel," l NEDE-24011-P-A-10-US . March 1991.
- 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 and {
NPF Edwin I. Hatch Nuclear Plant Units 1 and 2 (TACS 66524/66525)," l January 22,1988. :
- 3. " Supplemental Reload Licensing Submittal for Edwin I. Hatch Nuclear Plant i Unit 1, Reload 14, Cycle 15," General Electric Document 23A7206, !
Revision 0, April 1993.
- 4. "Edwin I. Hatch Nuclear Plant Units 1 and 2 SAFER /GESTR-LOCA f Loss-of-Coolant Accident Analysis," NEDC-31376-P. December 1986.
- 5. Bases for Specifications 3.3.F,3.11.A,3.11.B,and 3.11.C,Edwin I Hatch Nuclear Plant Unit 1 Technical Specifications .
f i
i 1
t
.i i
wp51colr15 15 May 1993 .
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