ML20111A955
| ML20111A955 | |
| Person / Time | |
|---|---|
| Site: | Hatch  |
| Issue date: | 05/07/1996 |
| From: | SOUTHERN NUCLEAR OPERATING CO. |
| To: | |
| Shared Package | |
| ML20111A951 | List: |
| References | |
| NUDOCS 9605140104 | |
| Download: ML20111A955 (22) | |
Text
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GEORGIA POWER COMPANY EDWIN L HATCH NUCLEAR PLANT UNIT 1 CYCLE 17 CORE OPERATING LIMITS REPORT Revision 0 Southern Nuclear Operating Company Post Office Box 1295 Birmingham, Alabama 35201 l
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9605140104 960507
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PDR ADOCK 05000321 p
l Edwin I. Hatch Nuclear Plant Unit 1 Cycle 17 Core Operating Limits Report i
i TABLE OF CONTENTS 1
Section 31tle East 1.0 Introduction 1
2.0 Rod Block Monitor 1
3.0 APLHGR Limit 2
4.0 MCPR Limit 11 5.0 APRM Flow Biased Simulated Thermal Power - High 18 Time Constant 6.0 References 18 1
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TABLE OF CONTENTS (Continued)
LIST OF FIGURES Figure No.
Iills P.agt 3-1 MAPLHGR Multiplier (MAPFACp ) Versus Core 3
Flow 3-2 MAPLHGR Multiplier (MAPFACp ) Versus Core 4
Power 3-3 APLHGR Versus Average Planar Exposure (GE9B-P8DWB330-10GZ-80M-150-T) 5 3-4 APLHGR Versus Average Planar Exposure (GE9B-P8DWB314-8G4.0-80M-150-T) 6 3-5 APLHGR Versus Average Planar Exposure (GE9B-P8DWB331-10GZ-80M-150-T) 7 3-6 APLHGR Versus Average Planar Exposure (GE13-P9HTB327-12GZ-100M-146-T-L UA-RECON) 8 3-7 APLHGR Versus Average Planar Expost.re (GE9B-P8DWB346-10GZ-80U-150-T) 9 3-8 APLHGR Versus Average Planar Exposure (GE12-P10HSB331-6G5.0/4G4.0-100T-150 '!)
10 4-1 MCPR Multiplier (Kp) Versus Core Power 14 4-2 MCPR Limits (MCPRs) Versus Core Flow 15 4-3 MCPR Limit Versus Average Scram Time 16 (with Turbine Bypass Yahes Operable andEOC-RPT System Operable) 4-4 MCPR Limit as Function of Average Scram Time 17 (with Turbine Bypass Valves Operable andEOC-RPT SystemInoperable) ii Revision 0
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TABLE OF CONTENTS (Continued)
LIST OF TABLES Table No.
Title Eage 4-1 Operating Flexibility Options Applicability 13 l
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iii Revision 0
l Plant Hatch Unit 1 Cycle 17 Core Operating Limits Report
1.0 INTRODUCTION
. The Core Operating Limits Report (COLR) for Plant Hatch Unit 1 Cycle 17 is prepared in accordance with the requirements of Technical Specification S.6.5. This document was also produced in accordance with the requirements of BWRCA procedure BCA 40-10 and is documented in a DRF under QA No. NFS-96-029. The core operating limits presented herein were developed using NRC-approved methods (References 1 and 2). Results from the fuel vendor's reload analyses for the fuel in Unit 1 Cycle 17 are documented in References 3 and 4.
The following cycle-specific core operating limits are included in this repon:
Control Rod Block Instrumentation - Technical Specification 3.3.2.1 a.
b.
Average Planar Linear Heat Generation Rate (APLHGR) - Technical Specification 2.1 Minimum Critical Power Ratio (MCPR) - Technical Specifications 3.2.2 I
c.
and 3.3.2.1 d.
APRM Flow Biased Simulated Thermal Power - High - Technical Specifications Surveillance Requirement 3.3.1.1.14 2.0 ROD BLOCK MONITOR (Technical Specification 3.3.2.1)
Both Rod Block Monitor (RBM) channels shall be operable as specified in Technical Specification 3.3.2.1 and when:
Thermal Power is 2 29% and < 90% of Rated Thermal Power, and MCPR is < l.70; a.
or b.
Thermal Power is 2 90% of Rated Thermal Power, and MCPR is < l.40.
1 Revision 0 l
Plant Hatch Unit 1 Cycle 17 Core Operating Limits Report 3.0 APLHGR LIMIT (Technical Specification 3.2.1)
The APLHGR limit for each fuel type is given by the applicable rated-power, rated-flow APLHGR limit taken from Figures 3-3 through 3-8, multiplied by the smaller of either:
a.
The flow-dependent multiplier, MAPFACr, from Figure 3 1, or b.
The power-dependent multiplier, MAPFACp, from Figure 3-2.
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 (Reference 1), the hand-calculated APLHGR values for a multi-lattice fuel (i.e., GE9-330, GE9-331, GE13-LUA, GE9-346, and GE12-331) must be less than or equal to the APLHGR limits shown in Figures 3-3, 3-5, 3-6,3-7, and 3-8, 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 3-3,3-5,3-6,3-7, and 3-8.
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Revision 0
1 Plant Hatch Unit 1 Cycle 17 Core Operating Limits Report i
i
~
~
///A--
0.se jl((f l
Ell ms
\\
[
im W
l 020 s
cArucc,.M,wAo Maruma g
i w
I MAPPAC,a MBAK2d N. MAPtM.7,]
3 0.70 l
l MAPMULTr 1 A POR PLOW > 81%
e
. =,an Ptow s.m l
0.60 l
Mparo, (r).MeeMtas [1.o,4+ s, p3
,, e a,u m cong a MAXNUM i
cons rum 0.50 l
(Y. RATM As op l
1er.s oAssi o.s7e4 l
l 107.o cAs74 OA758 j
i 112.0 04214 tLeso7 l
117A 0.3020 0.8806 1
,1 M
H N
N N
N
.2 CORE FLOW (% rated)
FIGURE 3-1 MAPLHGR MULTIPLIER (MAPFACr) VERSUS CORE FLOW 3
Revision 0
_. _. ~ _
Plant Hatch Unit 1 Cycle 17 Core Operating Limits Report 1.0 l
l 0.9 i
ig
/
i 0.5 spe0LE LOOP oPsRAftcel(sto) 0.75 -
= - -
- "u.*.*' " Mu"e"ru*an%n na t
uP 0.7 f
l g m,,,,
g w m m aggyggo k
s'P 4 30%:
I"'
I asAPPAc, = e.ses. esostad (P.30%)
j Ponsso% consFLow l0 p,
j i
c..
v.=>
E l T M # N oi g'
p i
.mc..
4=>
2' I
= =srt=>= "c'*"
%. m consnow l
,/ \\
o.4 g
52 20 26 30 40 50 80 70 00 90 100 POWER (% rated)
FIGURE 3-2 MAPLHGR MULTIPLIER (MAPFACp) VERSUS CORE POWER 4
Revision 0
i 1
l Plant Hatch Unit 1 Cycle 17 i
Core Operating Limits Report i
l l
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~
M L
- j q
u UNACCEPTABLE EXPOSURE OPERATION COORDINATES 11
~
X Y
E ROD 11.52 51 I 5
$.0 k
g' : :'
N 1.
,1.
a 100 12.10 g\\
9 E00 12.52 "E ll" ACCEPTABLE J
- = 1105 OPERATION
. l 100 1119 10.00 1130 11s0 1138 1s.00 1112 7
20.00 12.44 g
K 2s.00 11.n 3s.00 tais GE9B-PSDWB33010GZ 80M 180 T a
4s.co a.7s
\\
st.e4 s.70 e
s in is 20 2s 30 as so AVERAGE PLANAR EXPOSURE (GWdM)
MOST UMTING LATTICE AS A FUNCTION OF AVERAGE PLANMt expom=
FIGURE 3-3 AVERAGE PLANAR LINEAR HEAT GENERATION RATE VERSUS AVERAGE PLANAR EXPOSURE (Fuel Type: GE9B-P8DWB330-10GZ-80M-150-T) 5 Revision 0
Plant Hatch Unit 1 Cycle 17 Core Operating Limits Report Y
1.
e 3
/
\\
12 UNACCEPTABLE 3
BON
.j g)ga(g u e e m unares m
11 X
Y ECO 11A
~,
M 11A 10 7 1.00 ilo N
100 112 1 00 113 400 115 5
. j E00 117
." '28 ACCEMABLE a
. tu OPERAVON s 00 in 3
10.00 114 1130 115 d
1&00 132 7
. i 2tL00 115 h
J.
46.00 9.0
\\
GE9BMDWB3144C404DM 180 T 6 - l S1AT 6A ll mm,, - - _, ~. - - - -
0 5
10 15 20 25 M
35 40 46 80 AVERAGE RRMR EXPOSUE(GWWet)
FIGURE 3-4 AVERAGE PLANAR LINEAR HEAT GENERATION RATE VERSUS AVERAGE PLANAR EXPOSURE (Fuel Type: GE9B-P8DWB314-8G4.0-80M-150-T) 6 Revision 0
Plant Hatch Unit 1 Cycle 17 Core Operating Limits Report I
/WI
[
1 in UNACCEPTABLE ceOsuRs OPERATION COORDINATES k
~
j 1
N g
i am iisT tL20 11.02 10 -!
1.00 11.T5 D
1 00 11.96
}
f l
1 00 1117 g* m!
4.00 1141 5 00 iles g
l g*o ACCEPTABLE I, __;
a m i122 OPERATION i
O.00 1132 10.00 1125 1150 1113 y_
_i 15.00 1198
{
20.00 1115 l
e.' "t GE98 P8DWB33110GZ40M.150.T as 46.m s.it 1
80.00 5.06 g
},
i s
a a
eo 20 25 30 34 40 44 80 NOTE:
AVERAGE PLANAR EXPOSURE (OWd/st)
I Tus a THE APLHOR UANT FOR THE MOSY UnETING LATTICE AS A FUNCTION 0F AVERAGE PLANAR ExPoeuns l
1 I
FIGURE 3-5 AVERAGE PLANAR LINEAR HEAT GENERATION RATE VERSUS AVERAGE PLANAR EXPOSURE (Fuel Type: GE9B-P8DWB331-10GZ-80M-150-T) 7 Revision 0
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Plant Hatch Unit 1 Cycle 17 l
Core Operating Lhnits Report i
13 UNACCEPTABLE OPERATION f: ::
. 1 t
-)
EXPOSURE q
10 COORDINATES H
X Y
X Y
I
~
0,00 11M 12.5 11.70 9
~
(L30 11.14 15.0 11.70 1
~
1.00 11.32 17.5 11.70 2.00 11.58 20.0 11.56 100 11.70 25.0 10.56
(
a 4m ti.70 m0 10.1.
ACCEPTABLE 5.00 11.70 35.0 9.54 a00 t i.70 40.0 as0 OPERATION 7.00 11.70 45.0 8.25 7
1 00 11.70 50.0 7.57 l
l
'l
~
^
1 00 11.70 55.0 6.08 l
l 10.0 11.70 57.27 6.51
~
GE13 P9HTB32712GZ 100M-146-T LUA RECON e
a to il 20 25 30 35 40 45 50 SE NOTE:
AVERAGE PLANAR EXPOSURE (GWd/st)
THISIS THE APLHOR UnsT FOR1E WOS7 UANTING LAT110E AS A FUN 0710N OF AWEl%QE PL# TAR ExFoeunE i
FIGURE 3-6 l
AVERAGE " LANAR LINEAR HEAT GENERATION RATE VERSUS AVERAGE PLANAR EXPOSURE (Fuel Type: GE13-P9HTB327-12GZ-100M-146-T-LUA-RECON) 8 Revision 0
Plant Hatch Unit 1 Cycle 17 Core Operating Limits Report A
5:
~
f 5
UNACCEPTABLE 2
EXPOSURE OPERATION
,1
""7s8 q
N s,!
0.00 11.07 g 10 0.30 11.73 1.00 11.e4 l
!" ;i" N
5=
!" ll" N
{
1" ;i" ACCEPTABLE
(
i= ;;;
OPERATION
\\
10.00 12.70 12.50 12.06 7
15.00 12.52 20.00 11.91 h
2500 112 35.00 e.se GE9B-PSDWB34610GZ-80U-150-T g
4sm s.7s 51.71 SM y,
s l
AVERAGE PLANAR EXPOSU (GWdleQ j uos uwmotArnes AS A i pu am or memos pwm i ex u uns I man. -
FIGURE 3-7 AVERAGE PLANAR LINEAR HEAT GENERATION RATE VERSUS AVERAGE PLANAR EXPOSURE (Fuel Type: GE9B-P8DWB346-10GZ-80U-150-T) 9 Revision 0
1 Plant Hatch Unit 1 Cycle 17 Core Operating Limits Report i
i i
i EXPOSURE la cooRomTES X
Y X
Y ECO R12 12A0 180 UNACCEPTABLE im as" um am OPERATION
.00 an ism aa am am 17m aae 4.00 EM 20.00 E0e 6.00 1 81 25.00 EST E00 RST 30.00 1 14 10 7.00 9.73 36.00 7.71
&OD
.m.Est
. m 30, 4000 7 M
10.00 10.03 50.00 E43 g
11.00 EM M21 106 t
ACCEPTABLE q
r OPERATION s
i
....- -,4
.14 1
1 I
I I
I a
=
<a is 30 as 30 as e
a ao NOTT.:
AVERAGE PLANAR EXPOSURE (GWaput) wasonearmaR uns? PoRne MOST UmTING LA7710E AS A PUNF'M OF AVERedE PLANAR sxposunE j
l i
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FIGURE 3-8 AVERAGE PLANAR LINEAR HEAT GENERATION RATE VERSUS i
AVERAGE PLANAR EXPOSURE (Fuel Type: GE12-P10HSB331-6G5.0/4G4.0-100T-150-T) 10 Revision 0
Plant Hatch Unit 1 Cycle 17 Core Operating Limits Report 4.0 MCPR LIMIT (Technical Specification 3.2.2)
The MCPR operating limit (OLMCPR) is a function of core power, core flow, average i
scram time, fuel type, number of operating recirculation loops, operability of the end-of-cycle recirculation pump trip (EOC-RPT) system, and operability of the turbine bypass valves.
With both recirculation pumps in operation (TLO), the OLMCPR for each fuel type with various combinations of equipment operability, scram times, core flow and core power is determined as follows:
For 25% s power < 30%, the OLMCPR is given in Figure 4-1.
a.
- b. For power 2 30%, the OLMCPR is the greater of either:
- 1) The flow-dependent MCPR limit determined from the applicable mammum core flow limit line ofFigure 4-2, or 1
- 2) The product of the values from Figure 4-1 and the applicable Figures 4-3 and 4-4 as determined by Table 4-1.
As stated in the note on Figures 4-3 and t-4, with one recirculation pump operating (SLO), the calculated OLMCPR determined above is increased by 0.01.
In Figures 4-3 and 4-4, Option A scram time MCPR limits correspond to t = 1.0, where t is determined from scram time measurements performed in accordance with Technical Specifications Surveillance Requirements 3.1.4.1 and 3.1.4.2. Option B values correspond to t = 0.0. For scram times between Option A and Option B, the MCPR limit for each fuel type corresponds to T. If t has not been determined, Option A limits are to be used. Refer to Table 4-1 to determine the applicable set of fuel-type dependent curves.
I1 Revision 0
l Plant Hatch Unit 1 Cycle 17 Core Operating Limits Report l
The average scram time of the control rods, T, is defmed as:
1 Tm - TB t
= 0,or
, whichever is greater.
TA-Ts where:
TA
= 1.08 sec (Technical Specification 3.1.4, Table 3.1.4-1, scram time limit to notch 36).
1/2 Ni
+1.65
- o
- is
=
,[N,
,, ist where:
= 0.822 sec (mean scram time used in the transient analysis).
o
= 0.018 sec (standard deviation of p).
fNit im = '"!
E, Ni where:
n
= number of surveillance tests performed to date in the cycle.
Ni = number of active control rods measured in the ith surveillance test.
ti
= average scram time to notch 36 of all rods in the ith surveillance test.
Ni
= total number of active rods measured in Technical Specifications Surveillance Requirement 3.1.4.1.
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\\
Plant Hatch Unit 1 Cycle 17 Core Operating Limits Report TABLE 4-1 OPERATING FLEXIBILITY OPTIONS APPLICABILITY WITH:
USE:
EOC-RPT Turbine Bypass Valves -
Operable Operable Figure 4-3 Inoperable Operable Figure 4-4 Not licensed for this Operable Inoperable operating cycle Not licensed for this Inoperable Inoperable operating cycle NOTE:
Operation within the licensed power / flow region with a single recirculation loop and intermittent operation with reduced feedwater temperature are included in the MCPR limits presented in Figures 4-3 and 4-4.
13 Revision 0
Plant Hatch Unit 1 Cycle 17 Core Operating Limits Report 2.6
>50% FLOW 2.5 -
I
'/
l CPERATpio U8ST 80CPR(P)e Kp
- OPERATING Utsff BICPR(100)
FOR P
- 25% NO THERMRL ulsTS 800NfTOR980 REQU4 RED 14 NO UtgrTS SPECIPIED j
FOR 25% g P 4 P awaas (WHERE P ewaas e 30% POR HNP = 1,2)
~
Ke n (Kaw + 0.8200%. P)) i OUACPR (100) i AND 2.3 -
l Kan = 2.se PoR g se% CORE Plow i
Kaw = 2A0 POR
- st% Cofts PLOW 8
t FOR 30% g P < 45%
E Ke = 1.2s + o.e134 (4s%. PI 12 N
i FOR 43% g P 4 00W
~
ait 2 n.
kSO% FLOW Ke m ias
- o.coes7(so%.P) v$
2.1 -
FoR 60% 5 P:
K, = 1.o + e.oos7s (1oe%. P)
- n. u.
i Vl
- I 2.0 b
1.59 u.
1.4 I
l k
\\
1.3 -
l l
i i
i
.2
\\
i l
lN 1.1 -
j l P ***i' i
i 1.0 N
i i
6 i
i i
20 25 30 40 50 60 70 SO 90 100 POWER (% RATED)
FIGURE 4-1 MCPR MULTIPLIER (Kp) VERSUS CORE POWER 14 Revision 0
4 Plant Hatch Unit 1 Cycle 17 Core Operating Limits Report 1.7 MAXs4UGd PLOW RATE a
~
117 %
POR Wc (% RATED CORE FLOW)
- 40%
~
112 %
(
heCPRy n( AgW,i100 + By )'[1+0.0032 (40. W,)]
~
N 107%
FOR We (% RATED CORE FLOW)a 40%
ascPR pm asAx (12o, A,W, t too + s, )
N 1.5 117A
.eA32 1, sos 112A 4A02 1,747 197A
. ease issy 1.4 102A eA71 14ss W
N,KN 1.3 NN 1.2 1.1 i.
4 i i 30 40 50 60 70 80 90 100 110 120 CORE FLOW (% rated)
FIGURE 4-2 MCPR LIMITS (MCPRr) VERSUS CORE FLOW 15 Revision 0
l 1
I 1
Plant Hatch Unit 1 Cycle 17 Core Operating Limits Report 1.42 GE12 s
s 5.as 8
t,a GE13 k **
- g [s 8 1.32 E
12 b
GE9B -#
p.-
7 N
5 i
l'"_
f im
$.34 1.22 0
0.1 0.2 0.3 0,4 0.5 0.8 0.7 0.8 0.9 1
TAU (t)
NOTE: For SLO, increase the MCPR Limit obtained from this figure by 0.01.
FIGURE 4-3 MCPR LIMIT VERSUS AVERAGE SCRAM TIME (with Turbine Bypass Valves Operable andEOC-RPTSystem Operable) l l
i 16 Revision 0
l
\\
Plant Hatch Unit 1 Cycle 17 Core Operating Limits Report
{
1A2 l
1.8 q
p-E42 s#-
$ 1.=
d l
~
[ 1.44
- ~
GE13 7
g p-31A2 2
~
h1A a
- ' l s
GE9B 7
~
51.=
\\
s#
w r
p 1.34 121 1.3 1.25 0
0.1 03 0.3 0.4 0.5 0.8 0.7 OJ 0.5 t
TAU (t)
NOTE: For SLO, increase the MCPR Limit cbtained from this figure by 0.01.
FIGURE 4-4
~
MCPR LIMIT AS FUNCTION OF AVERAGE SCRAM TIME (with Turbine Bypass Valves Operable andEOC-RPTSystem Inoperable) 17 Revision 0 J
Plant Hatch Unit 1 Cycle 17 Core Operating Limits Report 5.0 APRM FLOW BIASED SIMULATED THERMAL POWER - HIGH Time Constant (Surveillance Requirement 3.3.1.1.14)
The allowable value for the APRM Flow Biased Simulated Thermal Power - High time constant is 5; 7.0 seconds.
6.0 REFERENCES
1.
" General Electric Standard Application for Reactor Fuel," NEDE-24011-P-A 111, November 1995.
2.
Letter, L. P. Crocker (NRC) to W. G. Hairston (GPC), " Issuance of Amendment No.168 to Facility Operating License DPR-57 and Amendment No.106 to Facility Operating License NPF Edwin I. Hatch Nuclear Plant Units 1 and 2 (TAC Nos.
73614 and 73615)," December 29,1989.
3.
" Supplemental Reload Licensing Report for Edwin I. Hatch Nuclear Plant Unit 1, Reload 16, Cycle 17," General Electric Document 24A5353, Revision 0, March 19%.
4.
"Edwin I. Hatch Nuclear Plant Units 1 and 2 SAFER /GESTR - LOCA Loss-of-Coolant Accident Analysis," NEDC-31376-P. December 1986.
18 Revision 0
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