ML20029E220
| ML20029E220 | |
| Person / Time | |
|---|---|
| Site: | Hatch  |
| Issue date: | 04/30/1994 |
| From: | GEORGIA POWER CO. |
| To: | |
| Shared Package | |
| ML20029E219 | List: |
| References | |
| NUDOCS 9405170281 | |
| Download: ML20029E220 (20) | |
Text
- -- --- - -- - - ---- -- -_ _ _ _
)O O
EDWIN I. HATCH NUCLEAR PLANT UNIT 2
'O CORE OPERATING LIMITS REPORT for FUEL CYCLE 12 O
l O
l O
l Revision 0 April 1994 O
F f C
66 P
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\\
l Interoffice Correspondence l o e..t P v L
l i
f DATE:
April 19,1994 O
as:
"etew ere!<1t sennori - tice, ies Core Operating Limits Report for Hatch 2 Cycle 12 Revision 0 File: Fuel Cycle Technical l
Log: IIL-3300
.(
' fe)' y>
/
l
[q FROM:
S. J. Bethay ALL UNIT 2 TECHNICAL l SPECIFICATIONS MANUAL HOLDERS TO:
l
)
l By amendment 106 to the Unit 2 Technical Specifications, 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 2 Technical Specifications manual holders a copy of Revision 0 of the COLR for Hatch 2 Cycle 12. This document should be utilized in conjunction with the Unit 2 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Please discard Revision 0 of the COLR for Hatch 2 Cycle 11, which was issued in November 1992, since it is no longer applicable. If you have questions regarding Revision 0 of the Unit 2 COLR for Cycle 12, please contact me at extension 8-821-7392 or telephone number (205) 877-7392.
SRP sp f
l nan r Enclosure O
cc: NORMS O
O
.mJq y summeu$
f.
O i ~O GEORGIA POWER COMPANY EDWIN 1. IIATC11 NUCLEAR PLANT UNIT 2 FUEL CYCLE 12 CORE OPERATING LIMITS REPORT REVISION 0 0
I l
Lo
. l Southern Nuclear Operating Company Post Office Box 1295 Birmingham, Alabama 35201 LO 4
________z__
EDWIN 1. IIATC11 NUCLEAR PIANT UNIT 2 FUEL CYCLE 12 CORE OPERATING LIMITS REPORT O
T^n's or cosTu"Ts l
Section Ittle Page O
1.0 Introduction 1
2.0 Rod Block Monitor 1
3.0 APLIIGR Limit 2
4.0 MCPR Limit 11 4.1 Two Recirculation Loop Operation 11
- O 4.2 siesie Recirceiettee LeeP o eretien 12 n
5.0 LilGR Limit 15 6.0 References
-15 O
l O
Revision 0 i
April 1994
__---_--__-_-_____-a
n-TABLE OF CONTENTS (Continued) l O-1 LIST OF FIGURES 1
Figure n
m
=
t LO i
3-1 MAPFACp 3
L 32 MAPFAC 4
p
-l 33 APLHGR Versus Average Planar Exposure
{
(GE7B-P8DRB284-7G4.0-80M-150-T) 5-I I
i 3-4 APLHGR Versus Average Planar Exposure I
(GE8B-P8DOB296-7GZ-80M 150-T) 6 l
3-5 APLIIGR Versua Average Planar Exposure (GE9B-P8DWB314-7G4.0-80M-150-T NOSHIP) 7 O
3-6
^ e L H G R v erse a verese Piemer E xP osere (GE9B-P8DWB314-804.0-80M-150-T) 8 37 APLHGR Versus Average Planar Exposure (GE11-P9 HUB 293-7G5.0/1G4.0-100M-146 T-LUA) 9 3-8 APLHGR Versus Average Planar Exposure
( G E9 B-P8 D W B314-8G 4.0A-80 M - 150-T) 10
-l 4-1 Power-Dependent MCPR Multiplier (K )
12 g
O 4-2 Flow-Dependent MCPR Limits (MCPRr) 13 I
4-3 MCPR Limit as Function of Average Scram Time 14 O
O 1
i Revision 0 ii April 1994
_ ~..
EDWIN 1. HATCH NUCLEAR PLANT
-j UNIT 2 FUEL CYCLE 12 CORE OPERATING LIMITS REPORT j
1.0 INTRODUCrlON 7
The Core Operating Limits Report (COLR) for Plant Hatch Unit 2 Cycle 12 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 methods (Refe-rences 1 and 2). Results from the reload analyses for the General Electric (GE) fuel in Unit 2 Cycle 12 are documented in References 3 and 4.
The following cycle-specific core operating limits are included in this report:
Control Rod Program Controls - Technical Specification 3/4.1.4.3.
a.
b.
Average Planar Linear lleat Generation Rate (APLIIGR) -
Technical Specification 3/4.2.1.
c.
Minimum Critical Power Ratio (MCPR) - Technical Specification 3/4.2.3.
d.
Linear IIcat Generation Rate (L.HGR) - Technical Specification 3/4.2.4 2.0 ROD BLOCK MONITOR (Technical Specification 3/4.1.4.3)
Both Rod Block Monitor (RBM) channels shall be operable as specified in O-Technical Specification 3/4.1.4.3 and when:
a.
TilERMAL POWER is < 90% of RATED THERMAL POWER l-and the MCPR is < 1.70 or b.
TIIERMAL POWER is.2. 90% of RATED THERMAL POWER-and the MCPR is < 1.40.
,g
>%)
- Revision 0 1
April 1994
9 Plant Hatch Unit 2 Fuel Cycle 12
. Core Operating Limits Report O
3.0 APLHGR LIMIT (Technical Specification 3/4.2.1)
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:
l a.
The factor given by Figure 3-1 or l
\\
l b.
The factor given by Figure 3M l
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.
i As required by GESTAR Amendment 19, the hand-calculated APLHGR values for a multi-lattice (i.e., GE8-296 and Gell-LUA) fuel must be less than or equal to the APLIIGR limits shown in Figures 3-4 and 3-7, respectively. When
.O
^ v ' " o n v"i"e> =re determi"ea 8 the vroee>8 ee m n"ter the iettiee-7 dependent APLHGR limits are used. Under these conditions, some axial locations may have APLHGR values exceeding the values shown in Figures 3-4
)
and 3-7.
l l
l i,
O O.
Revision 0 2
April 1994
Plant liatch Unit 2 Fuel Cycle 12 Core Operating Limits Report J
b l
g y 4@ gD 187 64 O
/
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igp os f'
~ <
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s is,%
eA A M $ t OW = $ $ I 0%
e so 0M O to M apt HORg = MAFT ACg
- M APtHORSID j
M apt HGRggy = ST AND ARD M APLHOR ttMITS I
M APT ACg = MINIMUM (MFRM)g, M APMULT,5 MAPMULT = 10 FOR f LOW > 81%
= 0 88 FOR ILOW s01%
[i MF HPD,IFl = MINIMUM l10,Ag + B,Fl U ' 'O F = FR ACilON OF R AllD CORE FLOW, AND A. B ARE FULL TYF'E Of PENDENT 7 y CONST ANIE GIVEN 8tt0W:
b F OR 7 X 7, M
b 3
8X8.8X8R RX9 lfA8 j
M A ktMUM CORE FLOW i
g o *o is R Anni "F
'F
^F
'F s
102 6 04898 0 8667 04861 08784 107 0 0 4421 08633 04674 0 8768 112 0 0 4074 08681 0 4214 0 8807 117 0 0 3701 G 9666 0 3878 0 8888 e $o 1
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FIGURE 3-1 MAPFACr Revision 0 3
April 1994
Plant Hatch Unit 2 FucI Cycle 12 Core Operating Limits Repod
\\
{-
I' tu M A Pl ltG H, e M APS A(,
- M APL HGM S t aND4RO M APl HGH t tuill M ape teGH o
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- 9 0 6 S IMMI)4 IP - 100%I 5
I 5 O H 6 2 % '. h O 0 " 'I I br# at = 0 75 i
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JS 80 40 go 60 70 30 t oss l'ipWI M 1% H A 1i DI I
1 FIGURE 3 2 M Al'FAC,.
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1 1
Revision 0 4
April 1994 1
____________________________________1_
Plant IIatch Unit 2 Fuel Cycle 12 Core Operating I.imits Report O
1
!O 14 1
4 i
i UNACCEPTABLE t
l OPERATION 13 i
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6 6
g -e e
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12.4 12.4 f \\
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1,0W EXPOSURE l
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2.0 11.2 s;
Je 11.5 OPERATION N.\\
6.0 11.8 l
H.0 12.1 9
10.0 12.3
_. _ ;; 1- - - - ^ ~ ~ - ~ ~ - -- -
12.4 12.4 FUEL TYPE:
\\
GE711.P8DR11284 7G4.0 8051150.T, t 8.5 0 i
1 s
0 5
10 15 20 25 30 35 40 45 Q
ArcRAGE Pl.ANAR EXPOSURE (GWd/st)
FIGURE 3-3 O
AVERAGE PLANAR LINEAR llEAT GENERATION ItATE VERSUS l
AVERAGE PLANAR EXPOSURE (Fuel Type: G E711-P8DRIl284-7G.4.0-80M-150-T)
Resision 0 5
April 1994
Plant Hatch Unit 2 Fuel Cycle 12 Core Operating Limits Report O
1 L
Q
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4 OPERATION -
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3 4.0 3238 8.0 12.73
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FUEL TYPE:
N i
j GE8B-P8DQB2907GZ-80M.150-T l O
5.u 0
10 15 20 25 30 35 40 45 50 AVERACE PIANAR EXPOSURE (GWd/st) f
'N5TE:
~
APLHOR LIMIT FOR MOST LIMITING LATTICE AS FUNCTION OF AVERAGE 1
PLAN AR EXPOSURE
.i FIGURE 3-4 I
AVERAGE PLANAR LINEAR IIEAT GENERATION RATE j
VERSUS AVERAGE PLANAR EXP,OSURE O
(Fuel Type: GE811-P8DQll296 7GZ-80M-150-T) l I
Revision 0 6
April 1994 1
i Plant Ilatch Unit 2 Fuel Cycle 12 Core Operating Limits Report O
.t(
/_,
13.is X
..} OPERATION i-
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COORDINATES l
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1.0 12.16 i
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f 913
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3.0 12.46
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5.0 12.79 iACCEPTABLE
%8 6.0 12.97 I
i OPERATION O
7-8.0 13.32 t-l l
+
+
9.0 13J6 j
10.0 13.43 J-FUELTYPD 6-12.5 13.50 GE9B.P8DWIl314-7G4.0-80M 150-T.NOSillP at 51.9
[
G W d/st 3
0 5
10 15 20 25 30 35 40 45 50 '
AVERAGE PLANAR EXPOSURE (GWd/st)
- (]
1 FIGURE 3 5 AVERAGE PLANAR LINEAR HEAT GENERATION RATE VERSUS AVERAGE PLANAR EXI.OSURE
'I
- \\
(Fuel Type: GE911-P8DWIl314-7G4.0-80M-150-T-NOSIIIP)
Revision 0 7
April 1994
Plant IIatch Unit 2 Fuel Cycle 12 Core Operating Limits Report O
O I
t 1
1 I
.,5 dN_,
j t
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-a ACCEPTABLE l
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j 7.
i2.8 H.0 12.91
' OPERATION l
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9.0 12.9M l
l I
10.0 13.08 j
6 g;,3 3 3,g g FU El. TYPE:
,_i
__i GE98.PNDWR314-8G4.0-bONI.150.T l
5.70 l 4p 5
0 5
10 15 20 25 30 35 40 45 50 AVERAGE PLANAR EXPOSURE (GWd/st)
O FIGUltE 3-6 O
avEitacE >>Easait tisE4R iiE4r GExEitarios itarE VEllSUS AVERAGE l'LANAlt EXPOSURE
( Fuel Tvpe: G E9 B-P8 DWll314-8GA.0-80M-150-T)
O
~
Revision 0 8
April 1994
Plant IIntch Unit 2 Fuel Cycle 12 Core Operating Limits Report O
1 l
l
- O
~
1 t
l 13 -
i fUNACCEPTABLE
' OPERATION I
i2 W
$~ $ 11.66 l11.70 N
.f
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t 11 LOW EXPOSURE 3 g!jf N
i COORDINATES N'
1 l
j 10.60 i
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l 1Om E
17.5 11.70 I
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___l ACCEPTABLE 7 7
O i OPERATION i
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l l
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FUEL TYPD (GEllLUA)
,7 G E l l.1911 U B293 7 G5.0/l G4.0 10051 146.T.1,UA i
0 5
10 15 20 25 30 35 40 45 50 AVERAGE PLANAR EXPOSURE (GWd/st)
O
'NdTE:
APLHGR LIMIT FOR MOST LIMITING LATTICE AS FUNCTION OF AVERAGE PLANAA EXPOSURE O
nGUitE 3 2 AVEllAGE PLANAll LINEAll HEAT GENEllATION IRATE VEllSUS AVEllAGE PLANAll EXI?OSUllE qv (Fuel Type: G El1-P911Ull293-7G5,0/lG4.0-100M-146-T-LUA)
Revision 0 9
April 1994 m
-_---_m__
=
Plant flatch Unit 2 Fuel Cycle 12 Core Operating Limits Report lO l
O ex;XT 1
i i
1 1
p* 7 13.14
'~
- . UNACCEPTABLE :
8 12.44 ' K
- OPERATION:
i i2 - - ' ' - >
x 11.79 l
I,0W EXPOSURE l J
+
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.j _
g COORDINATES s
x y
10.47 l f
l 3 -
0.0 11.80 b
0.2 11.87 i
l 5
1.0 11.98 i
J 4
2.0 12.15 l
l 9.13 9
f h
3.0 12.33
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4.0 12.52 i
i
)
l
- ACCEPTABLE-t g
8-5.0 12.72 6.0 12.93 i
j i OPERATION l
!O 7-8.0 13.20 j
j y
9.0 13.28 l
l 10.0 13.38 l
6-12.5 13.48 FUEL TYPD 5.89 j
GE9B.P8DWB314 8G4.0A40M 150-T l
l 5
0 5
to 15 20 25 30 35 40 45 50 AVERAGE PLANAR EXPOSURE (GWd/st)
O FIGURE 3-8 AVERAGE PLANAR LINEAR 11 EAT GENERATION RATE VERSUS AVERAGE PLANAR EXP.OSURE O
(FU EL 'IYPE: G E911-PSDWil314-8G4.0A-80M-150-T)
Revision 0 10 April 1994
Plant Hatch Unit 2 Fuel Cycle 12 Core Operating Limits Report
- O 4.0 h1CPR LlhilT (Technical Specification 3/4.2.3)
The NICPR operating limit (OLh1CPR) 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 1.22 for GE7B, GESB, and GE9B fuels, and 1.28 for Gell fuel.
Os 4.1 Two Recirculation Loon Operation For 259E.1 power < 309c, the OLMCPR is given in Figure 4-1. For power 2. 3092, the OLhiCPR is the greater of either:
a.
The applicable limit determined from Figure 4-2 or O
The everegriete u 8 vee ie risere 4-1. meitivirea hr the i
a.
r appropriate limit shown in Figure 4-3. The scram time dependence is given in the Bases for Technical Specification j
3/4.2.3.
l 4.2 Single Recirculation I 000 Operation For single-loop operation the OLMCPR shall be 0.01 greater than the two loop value which is determined as specified in section 4.1.
O Revision 0 11 April 1994 1-
Plant Hatch Unit 2 Fuel Cycle 12 Core Operating Limits Report O
O l
2.6 -
> 50% FLOW 7 3pERATING LIMIT MCPR(P) = Kp
- OPERATING LIMIT MCPR(100) l FOR P < 25% : NO THERMAL LIMITS MONITORING REQUIRED NI NO LIMITS SPECIFIED 14 g 3; FOR 25% < P < P mus (WHERE P mas = 30% FOR HNP 2)
$A 23-Kp = [Km + 0.02(30% - P)]/OLMCPR(100)
V AND A k 2.2 -
Km = 2.00 FOR < 50% CORE FLOW L
K "= 2.40 FOR > 50% COPE FLOW VjE
<50%
$ $ 2.1 --
~
FLOWr-FOR 30% $ P < 45% :
Mg Kp = 1.28 + 0.0134 (45%-P) t2 FOR 45% $ P < 60% :
@ g 2.0 - -13." g L '
m E
Kp = 1.15 + 0.00867 (60% - P)
[ f:
-~
Kp = 10 + 0.00375 (100%-P)
FOR 60% < P :
g ud 7. i.4 I
1 O I
O 13 f
l 1..
3 1.1 IbYPASS-i 1.0 20 25 30 40 50 60 70 80 90 100 POWER (% RATEl))
O FIGURE 4-1 POWER-1)El'ENI)ENT MCPR MULTIPLIER (K )
O p
Revision 0 12 April 1994
Plant Hatch Unit 2 Fuel Cycle 12 Core Operating Limits Report OV O
l 1.7
/3 MAXIMUM F14W RATE =
Q
}
FOR We (% RATED CORE FIDW) > 40%
117 %
MCPR(19= MAX (1.20, AfWc/100+B0 112 %
1.6 -\\
/
/' /
- 107%
MAX FLOW Af Bf
/ / - 102.5%
117.0
-0.632 1.309
/
112.0
-0.602 1.747 1.5 4
107.0
-0.586 1.697
\\.!
'/
l 102.5 0.571
-1.655 L
i
/,
y
/
O h
i 1.3
.. _. d__
l l
1.2 --
+ - - -
l t
FOR We (% RATED CORE FLOW) < 40%,l j
MCPR(F)=(AfWe/100+ BO i
- [1 + 0.0032(40.We)]
i l
l' 1.1 -
30 40 50 60 70 80 90 100 110 120 fg CORE FLOW (% rated)
U i
FIGURE 4 2 FLOW-DEPENDENT MCPR LIMITS (MCPR )
.O y
Revision 0 13 April 1994
)
i
Plant Ilatch Unit 2 Fuel Cycle 12 Core Operating Limits Report
(~
lU 1.29 l
l i
l l
l l
f l
I l
l I
'(O 1.28
]
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)
Gell i
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1.27
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,0 l
l I
1.26
+-
W 4
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t C 1.25 I
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GE9B i
t
.i i
7 1.24
+---
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C l
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a 3 23 N
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g
_1.
GE711 AND L i
.22 i
i I
u I
5 GE8B i
c f
1.21 u
i E
1.20 o
C 1.19 0.0 0.1 0.2 0.3 0.4 0.5 0.6 0,7 OE 0.9 1.0 TAU 1'
FIGUltE 4-3 l
p N1CI'It LIN11T AS FUNCTION OF AVERAGE SCitAM TIME l
d I
i Revision 0 14 April 1994
Plant Hatch Unit 2 Fuel Cycle 12 O
Core Operating Limits Report O
5.0 LHGR LIMIT (Technical Specification 3/4.2.4)
L The LHOR limit is 13.4 kW/ft for GE7B fuel. The LHGR limit for GE8B, GE9B, and Gell fuels is 14.4 kW/ft.
(O l
6.0 REFERENCES
i 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.168 and 106 to Facility Operating Licenses DPR 57 and NPF Edwin 1. Hatch Nuclear Plant Units 1 and 2 (TACS 66524/
66525)," January 22,1988.
3.
" Supplemental Reload Licensing Submittal for Edwin I. Hatch Nuclear Plant Unit 2, Reload 11, Cycle 12," General Electric Document 23A7241, Revision 0. April 1994.
4.
"Edwin I. IIatch Nuclear Plant Units 1 and 2 SAFER /GESTR-LOCA Loss-of-Coolant Accident Analysis," NEDC-31376-P, December 1986.
5.
Edwin 1. Hatch Nuclear Plant Unit 2 Technical Specification _s, Bases 3/4.1.4.3, 3/4.2.1. 3/4.2.3, and 3/4.2.4.
O Revision 0 15 April 1994
_ _ - _ _ _ _