ML20128L965
| ML20128L965 | |
| Person / Time | |
|---|---|
| Site: | Limerick  |
| Issue date: | 07/08/1996 |
| From: | Carmody J, Giancatarino A, Mchale J PECO ENERGY CO., (FORMERLY PHILADELPHIA ELECTRIC |
| To: | |
| Shared Package | |
| ML20128L954 | List: |
| References | |
| PECO-COLR-L2R3, PECO-COLR-L2R3-R01, PECO-COLR-L2R3-R1, NUDOCS 9610150245 | |
| Download: ML20128L965 (37) | |
Text
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s l PE,CO Nuclo e, Fuol & S0rvicO3 Divicion PECO-COLR-L2R3 L2R3 Core (perating Limits Report Page 1, Rev. 1 4
CORE OPERATING LIMITS REPORT l
FOR LIMERICK GENERATING STATION UNIT 2 RELOAD 3, CYCLE 4 j
l
$ bNd b,fD D Prepared By:
Date:
l J.
L. McHale Engineer Reviewe Ad Date:
I A.
Gialacatarino Independent Reviewer 6
Approved By:_
/ Leo
. Date:
d J. M. Carmody Manager Nuclear Design Branch 9610150245 961004 PDR ADOCK 0500 3
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l PECO NuclCrar, Fuol & S0rvicOc Divicien PECO-COLR-L2R3 L2'R3 Core Operating Limits Report Page 2, Rev. 1 i
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LIST OF EFFECTIVE PAGES Page(s)
Revision 3-5,8-17,27,28,34-36 0
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PZCO Energy, Fuol & Services Division PECO-COLR-L2R3 L2R3 Core Operating Limits Report Page 3, Rev. O INTROuvCrlON m Sm"LRY This report provides the cycle-specific parameter limits for:
Maximum Average Planar Linear Heat Generation Rate (MAPLHGR);
Minimum Critical Power Ratio (MCPR);. ARTS MCPR thermal limit adjustments and multipliers; ARTS MAPLHGR thermal limit multipliers; Rod Block Monitor (RBM) s,etpoints; MAPLHGR single loop operation (SLO) reduction factor; Linear Heat Generation Rate (LHGR); Turbine Bypass Valve parameters; Recirculation Pump Motor Generator (MG) Set. Scoop Tube-Stops; and Reactor Coolant - System Recirculation Flow Upscale Trips for Limerick Generating Station Unit 2,
Cycle 4.
These values have been determined using NRC-approved methodology and.are established such that all applicable limits of the plant safety analysis are met.
This report is submitted in accordance with Techniceal Specification 6.9.1.9 of Reference 1.
Preparation of this report l
l was performed in accordance with PECO Energy Company, Fuel &
Services Division Procedure FM-105.
l This report contains all thermal limit parameters related to i
the implementation of the ARTS Improvement Program and Maximum Extended Load Line' Limit analyses (ARTS /MELLLA) for Limerick 2 Cycle 4.
This is the first application of ARTS /MELLLA at Limerick Generating Station Unit 2.
i MAPLHGR LIMITS The limiting MAPLHGR value for the most limiting lattice
)
(excluding natural uranium) of each fuel type as a function of average plancr exposure is given in Figures 1 through 10.
These figures are used when. hand calculations are required as specified in Technical Specification 3.2.1.
No. reduction in MAPLHGR limits is required under ARTS during single loop operation (Table 2).
MCPR_LZNIH The MCPR value for use in Technical Specification 3.2.3 for each fuel type is given in Figures 11 through 19.
Information regarding the validity of these MCPR limits in various operating domains and for SLO is also provided.
The MCPR values shown in these figures are the bounding values for all points on the power flow map including Maximum Extended Load Line Limit (MELLL) down to 81% of rated core flow during full
. power operation, Increased Core Flow (ICF) up to 110% of rated core l
flow, Rated Core Flow (RCF, the area between the MELLL and ICF operating domains), Feedwater Temperature Reduction (FWTR) up to 105oF during Power Coastdown' operation and Feedwater Heater Out of i
Service (FWHOOS) up to 60 F feedwater temperature reduction at any time during the cycle prior to Power Coastdown operation.
Bounding MCPR values are also provided for inoperable-Recirculation Pump Trip (RPTOOS) or inoperable Steam Bypass System (TBVOOS). These two options represent the Equipment Out of Service i
~-
PECO. Energy, FuOl & S rvices Division PRCO-COLR-L2R3 L2R3 Core Operating Limits Report Page 4, Rev. 0 (EOOS) condition.
Note in these figures the term " EOR" refers to.the cycle exposure at which operation at " rated conditions" is no longer possible (i.e.,
the cycle exposure at which cycle extension begins).
The cycle exposure which represents " EOR" is given in the latest verified and approved Cycle Management Report.
This value can change during the cycle due to changes in operating strategy.
4 ARTS THERMAL LIMIT ADMINISTRATION ARTS provides for power-and flow-dependent thermal limit adjustments and multipliers which allow for a more reliable administration of the MCPR and MAPLHGR thermal limits.
The flow-dependent multiplier MAPFAC(F) and flow-dependent adjustment MCPR(F) are suf ficiently generic to apply to all fuel types and operating domains.
However, there are two sets of power-dependent MAPLHGR multipliers for with-and without-EOOS conditions.
- Also, there are two sets of power-dependent MCPR adjustments and multipliers for with-and without-EOOS conditions.
These adjustments and multipliers are shown in Figures 20 through 25.
ROD BLOCK MONITOR SETPOINTS The ARTS RBM provides for power-dependent RBM trips to replace the previous flow-dependent trips.
The trip setpoints and applicable RBM signal filter time constant data are shown in Table 1.
LINEAR HEAT GENERATION RATES The LHGR value for each fuel type for use in Technical Specification 3.2.4 is given in Table 3.
STEAM BYPASS SYSTEM OPERUILITY The operability requirements for the steam bypass system for in Technical use Specifications 3.7.8 and 4.7.8.C are found in Table 4.
If these requirements cannot be met, the MCPR, MCPR(P) and MAPFAC (P) limits for inoperable Steam Bypass System, known as Turbine Bypass Valve Out Of Service (TBVOOS), must be used.
PIOiRCULATION PUMP TRIP OPERABILITY If the recirculation pump trip is inoperable, the MCPR, MCPR(P) and MAPFAC(P) limits for Recirculation Pump Trip Out Of Service (RPTOOS), must be used.
PECO Energy, Fuel & Services Div.sion PECO-COLR-L2RO L2R3 Core Operating Limits Repoict Page 5, Rev. O RECIRCULATION PUMP MOTOR-GENERATOR (MG) SET SCOOP TUBE STOPS The electrical and mechanical stops are set to limit the reactor core coolant flow rate during an event in which the recirculation flow rate increases to its maximum value.
Technical Specification Surveillance Requirement number 4.4.1.1.2 requires that each pump MG set scoop tube mechanical and electrical stop shall be demonstrated OPERALuE, with overspeed setpoints less than or equal to specified values, at least once per 24 months.
These values are cycle specific and can be found in Table 5 of this COLR.
CONTROL ROD BLOCK INSTRUMENTATION REACTOR COOLANT SYSTEM RECIRCULATION FLOW UPSCALE TRIP Technired Specification Limiting Condition for Operation number 3.7 d rem 2 ires control rod block instrumentation channels shall be OPERMA..E with their trip setpoints consistent with the values showa,Ln ;he Trip Setpoint column of Technical Specification Table 3.3.6-2.
The Reactor Coolant System Recirculation Flow Upscale Trip is a cycle specific value and as such is found in Table 6 of this COLR.
Table 6 lists the Nominal Trip Setpoint and Allowable value.
QUALIFICATION FUEL BUNDLES LGS Unit 2 Cycle 4 will be the third cycle of irradiation for the QFBs.
The thermal limit basis for the ABB and SPC QFBs are specified in References 6 through 10.
The limiting MAPLHGR values for the ABB and SPC QFBs (Figures 7 and 8) are based on the original MAPLHGR values for the JE9B-P8CWB325-9GZ2-80M-150 bundle (Reference 5) and not the revised values (Reference 3).
The MCPR values for the ABB and SPC QFBs are calculated based en the MCPR values of the GE9B-P8CWB325-9GZ2-80M-150 bundle (References 2 and 11). Specific values for all thermal limits are given for the Gell QFBs (LUA304).
DEBRIS FILTER BUNDLES Limerick Unit 2 Cycle 4 is the first PECO Energy Cycle in which a GE Fuel Bundle fitted with a debris-resistant lower tie plate (LTP) is used.
Four of the Reload 3 Gell fuel bundles will be equipped with these debris-resistant LTPs.
The debris filter bundles will be modeled the same as the Reload 3 Gell bundle (P9 CUB 399-14GZ). Therefore, they will have the same cycle specific
' parameter limits.
The use of these debris-resistant LTP bundles is justified in References 15 and 16.
l PECO Nuclocr, Fuci & S3rvic03 Division PECO-COLR-L2R3 L2'R3 Core Operating Limits Report Page 6, Rev. 1 SAFETY LIMIT MINIMUM CRITICAL POWER RATIO (SLMCPR)
The Safety Limit Minimum Critical Power Ratio (SLMCPR) for Limerick 2 Cycle 4 has been recalculated by General Electric.
The new analysis yields a SLMCPR of 1.10; 0.03 higher than previously reported.
This change has been incorporated into the COLR as per the directions of Reference 17.
A revision to the Supplemental Reload Licensing Report, Reference 18, has been issued to document j
the ef fect on Operating Limit Minimum Critical Power Ratio (OLMCPR) due to the change in SLMCPR.
In addition, the Reference 19 letter documents the changes to the ARTS (power and flow) MCPR curves due l
to the increase in SLMCPR.
REFERENCES 4
1)
" Technical Specifications and Bases for Limerick Generating Station Unit 2",
Docket No. 50-353, License No. NPF-85.
3 2)
" Supplemental Reload Licensing Report for Limerick Generating Station Unit 2 Reload 3 Cycle 4",
General Electric Company Document No. 24A5168, Rev. 0, January 1995.
3)
" Lattice Dependent MAPLHGR Report for Limerick Generating Station Unit 2 Reload 3 Cycle 4", General Electric Company Document No. 24A5168AA, Rev. O, January 1995.
4)
"Lottice-Dependent MAPLHGR Report for Limerick Generatinq Station Unit 2 Reload 2 Cycle 3", General Electric Company Document
?
No. 23A7200AA, Rev. 3, July 1994.
5)
" Basis of MAPLHGR Technical Specifications for Limerick Generating Etation Unit 2",
NEDC-31930P, April 1991.
6)
" Supplemental Lead Fuel Licensing Report, SVEA-96 Lead Fuel Assemblies for Limerick-2, Summary", ABB Atom Report BR 91-042, January 1991.
7)
" Limerick-2 9x9-9X+ Qualification Fuel Assembly Safety Analysis Report", ANF-9 0 -193 ( P), Revision 1, September 1992.
8)
Letter, W. R. Harris to A. M. (lson, " Revised LGS-2 SVEA-96 Lead Fuel Assembly (LFA) LOCA Limits", April 26, 1993, t
9)
- Letter, H.
G.
Shaw to Manager Fuel Management Section,
" Relaxation of LHGR and MAPLHGR limits for the 9x9-9X
+
Qualification Fuel Assemblies (QFAs) for Limerick", May 13, 1993.
10)
" Supplemental Lead Fuel Assembly Licensing Report, SVEA-96 LFAs for Limerick 2",
ABB Report UK 90-512, September 1991.
11)
Calculation Sheet prepared by J.
F.
- Buckley, "OLMCPR Limits for L2C4", DRF No. f.404, January 3, 1995.
_. - -. ~.,
l PECO Nuc1Cor, Fu 1 & SOrvicGO Divicion PECO-COLR-L2R3 L2'R3 Core Operating Limits A3 port Page 7, Rev. 1 REFERENCES (CONT.)
12:
" Maximum Extended Load Line Limit and ARTS Improvement Program Analyses for Limerick Generating Station Units 1 and 2",
GE Nuclear Energy Document No. NEDC-32193P, Rev.2, October 1993 13)
- Letter, G.
V.
Kumar to K.
M.
McGinnis,. " Limerick ARTS Application with Equipment Out-of-Service (EOOS)", Dec. 10, 1993.
14)
" Power Rerate Condition Setpoint Calculations for the Philadelphia Electric Company Limerick Generating Station Units 1
&2",
Document NO. GE-NE-2 08-2 0-0993 -2, August 1994.
i 15)
Letter, R. M. Butrovich to H. J. Diamond, " Safety Review of the Limerick 2 Cycle 4 Revised Loading Pattern" January 20, 1995.
16)
ECR No.
LG 94-11314 "DEC for Use of GE-11 Debris Resistant Lower Tie Plate" 17)
Letter, R. M. Butrovich to H. J. Diamond, " Limerick Unit 2 Safety Limit MCPR", May 21, 1996.
18)
" Supplemental Reload Licensing Report. for Limerick Generating Station Unit 2 Reload 3 Cycle 4",
General Electric Company Document No. 24A5168, Rev. 1, June 1996.
19)
- Letter, R.
M.
Butrovich to H.
J.
Diamond, " Limerick 2 Reload 3 (Cycle 4) SRLR Revision 1",
June 14, 1996.
. ~. _..
+
P CO Energy, Fuel & Services Division PECO-COLR-L2R3 i
L2R3 Core Operating' Limits Report Page 8, Rev. 0 i
Figure 1 MAEIMUM AVERAGE PLANAR LINEAR HEAT GENERATION RATE (MAPLEGR) VERSUS 9
AVERAGE PLANAR EEPOSURE FUEL TYPE P9 CUB 399-14GZ (Gell)
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(kW/ft) 0.0 10.57 7.0 11.67 25.0 10.75 0.2 10.63 8.0 11.82 30.0 10.14 1.0 10.76 9.0 11.95 35.0 9.53 2.0 10.95 10.0 12.09 40.0 8.91 3.0 11.10 12.5 12.13 45.0 8.27 4.0 11.24 15.0 11.97 50.0 7.60 5.0 11.38 17.5 11.68 55.0 6.90 6.0 11.53 20.0 11.37 57.1 6.59 I
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PECO Energy, Fuel is Services Division PECO-COLR-L2R3 L2R3 Core Operating Limits Report Page 9, Rev. 0 Figure 2 MAXIMUM AVERAGE PLANAR LINEAR HEAT GENERATION RATE (MAPLEGR) VERSUS AVERAGE PLANAR EXPOSURE FUEL TYPE P8CIB219-4GZ (GE6)
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PECO* Energy, Fuel & Services Division PECO-COLR-L2R3 L2R3 Core Operating Limits Report Page 10, Rev. O Figure 3 MAXIMUM AVERAGE PLANAR LINEAR HEAT GENERATION RATE (MAPLHGR) VERSUS AVERAGE PLANAR EXPOSURE FUEL TYPE P8CIB176-4GZ (GE6)
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P~CO Energy, FuO1 & Services Division PECO-COLR-L2R3 L2R3 Core Operating Limits Report Page 11, Rev. O Figure 4 MAXIMUM AVERAGE PLANAR LINEAR HEAT GENERATION RATE (MAPLHGR) VERSUS AVERAGE PLANAR EEPOSURE FUEL TYPE P9 CUB 354-12GZ2 (Gell) f 13.0 l
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.PECO Energy, Fual & Services Division PECO-COLR-L2R3 L2R3 Core operating Limits Report Page 13, Rev. O Figure 6 MAXIMUM AVERAGE PLAN 3'R LINEAR HEAT GENERATION RATE (MAPiHGR) VERSUS AVERAGE PLANAR EAPOSURE FUEL TYPE P9 CUB 304-LUA (Gell) u.o l
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PECO' Energy, Fuel & Services Division PECO-COLR-L2R3 L2R3 Core Operating Limits Report Page 14, Rev. O Figure 7 MAXIMUM AVERAGE PLANAR LINEAR HEAT GENERATION RATE (MAPLNGR) VERSUS AVERAGE PLANAR EXPOSURE FUEL TYPE ABB SVEA-96 (QFR)
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(kW/ft) 0.0 12.23 6.0 13.33 20.0 13.01 0.2 12.31 7.0 13.49 25.0 12.36 1.0 12.47 8.0 13.65 35.0 11.01 2.0 12.70 9.0 13.81 45.0 9.44 3.0 12.89 10.0 13.95 50.9 6.29 4.0 13.03 12.5 13.95 5.0 13.18 15.0 13.64
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l PCCO NucicCr, FuOl & SOrvicO3 DiviDicn PECO-COLR-L2R3 L2R3 Core Operating Limits Report Page 20, Rev. 1 FIGURE 13 MCPR vs. TAU THIS FIGURE IS VALID FOR ALL GE FUEL TYPES (TBVOOS)
This figure is valid for two-loop operation.
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l l PpCO NuclOOr, Fuol & SOrvicOc Division PECO-COLR-L2R3 L2R3 Core Operating Limits Report Page 21, Rev, 1 FIGURE 14 NCPR vs. TAU THIS FIGURE IS VALID FOR THE ABB SVEA-96 QFB (RCF, MELLL, ICF, FMTR, AND FWHOOS)
This figure is valid for two-loop operation.
For single-loop operation, increase any value obtained from the figure by 0.02.
4 THIS FIGUAE IS AEFEAPED TO BY 1.52 TECHNICAL SPEClFiCATION 3,2.3
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L2R3 Core Operating Limits Report Page 22, Rev. 1 FIGURE 15 l
MCPR vs. TAU THIS FIGURE IS VALID FOR THE ABB SVEA-96 QFB (RPTOOS)
This figure is valid for two-loop operation.
For single-loop operation, increase any value obtained from the figure by 0.02.
1.68 1.68 THIS FIGURE IS REFEAAED TO BY
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\\ PECO NuclOOr, Fu31 & S rvicOc Divicion PECO-COLR-L2R3 L2R3 Core Operating Limits Report Page 23, Rev. 1 FIGURE 16 MCPR vs. TAU THIS FIGURE IS VALID FOR THE ABB SVEA-96 QFB (TBVooS) l This figure is valid for two-loop operation.
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Oct. 8 T
Oct. A
j
^*
I P,ZCO NuclCnr, FuOl & SOrvicOO Divicion PECO-COLR-L2R3 L2R3 Core Operating Limits Report Page 24, Rev. 1 FIGURE 17 NCPR vs. TAU THIS FIGURE IS VALID FOR THE SPC 9x9-9X+ QFB (RCF, MELLL, ICF, FWTR, AND FWHOOS)
This figure is valid for two-loop operation.
For single-loop operation, increase any value obtained from the figure by 0.02.
1.52 1.52 THIS FIGUAE IS AEFEAAED TO 8Y TECHNICAL SPECIFICATION 3.2.3
'(
1.50 goc' 1.50
&* pi, o f.-
CC 1
1.48 )
1.48 g
- s'4 1
p>-
,>+
1.46 1.46
)
1,44 1.44 I
I I
I i
I I
I O.0 0.1 0.2 0.3 0.4 0.5 0.6 0.7 0.8 0.9 1.0 Opt. 8 Opt. A
l P;CO NuclOOr, FuOl & S0rvicO3 Divicign PCCO-COLR-L2R3 L2R3 Core Operating Limits Report Page 25, Rev. 1 FIGURE 18 MCPR vs. TAU THIS FIGURE IS VALID FOR THE SPC 9x9-9X+ QFB (RPTOOS)
Phis figure is valid for two-loop operation.
For single-loop operation, increase any value obtained from the figure by 0.02.
THIS FIGURE IS REFERREO TO BY 1.64 TECHNICAL SPECIFICATION 3.2.3 1.64 1,62 h>
1.62 s
g 1.60 8
1.60
/
O-1.58 (1.58 g
2 1,56 )
1.56
./
m
,a 1.54 1.54 1.52 )
1.52 I
I I
I I
I I
I I
O.0 0.1 0.2 0.3 0.4 0.5 0.6 0.7 0.8 0.9 1.0 opt. e Opt. ^
l P5CO NuclCOr, Fu31 & SG1.vic D DiviCion PZCO-COLR-L2R3 L2R3 Core Operating Limits Report Page 26, Rev. 1 FIGURE 19 MCPR vs. TAU THIS FIGURE IS VALID FOR THE SPC 9x9-9X+ QFB (TBVOOs)
This figure is valid for two-loop operation.
For single-loop operation, increase any value obtained from the figure by 0.02 THIS FIGUAE IS AEFEAAED TO BY TECHNICAL SPECIFICATION 3.2.3 1.56 (1.56
(
em 1
4 1.54 8
(1.54 cc
$, +
Q.
o2 p + #'
1.52) 1.52
)
1.50 1.50 i
t i
I I
I I
I I
O.0 0.1 0.2 0.3 0.4 0.5 0.6 0.7 0.8 0.9 1.0
{
Opt. 8 Oct. A
t* w uM NO WO' l=H hf H
n8 1.2 m
eN q
DQ H
H w
U-O e
[$
1.0 H
H " t2 m
N Qv i
v em
-e o
$H i
tt 0.9 H
- 4 i
0-O tt W i
nG
\\
f w
e l
g OO Wu i
g jg 4No g
O o.e343 0.6 i " "**
Wh kk N
IL 8
O MW I
' o 55 H
N n
NN
,0.50 m (p) gAPFAC (P)
- EP@LIGI (etd) aaAPLICR (etd) = Standard aaAPLHCit Lamite Q
{
> EoK Flow Eg H
0.4 For 25m > P: No Therme Liette tenitorino Required g
g g,
M f
sem Lemets spectfled Q.
For 25N = P = 30s: taAPFAC (P) = 0.55
- 0.034 (P - 305) y9 g
r,.o. -.,.ow U
0.2 -
naAPFAC (p) = 0.50 + 0.004 (P - 30s) g For > Sou Core Flow H4 4 "g
gg For 3cm = P: naAPFAC (P) - 1.0. o.cos224 (P - scos)
QO I
l
$w eO l
l l
I l
I i
o,o h
y O
10 20 30 40 50 60 70 80 90 100 g
POWER (% Rated) w t*
<u V
p
~; \\'
e W
O 1;
il
t* ht MN NO g
uO H
O 01 0
1.2 N
+5 %
Ca q.
O M
91 M H
WG N
1.0 OH tt e g tn y vH U
v Q
N
$4 A*
y u"l Er
=a g 0.8 hy 2
O tt p-4 0
as n H
e E
08 Nm o
o q
e b
84 p
H UU
< 0. 5 HON Q
O P-g tL g EON Flow 0.55 g5N M4 g
Q rt p N
g
>0.53 e.g g
tu mPte CP) = WPFAC (P) a mPLHGR (etc0 0
N P-0.48 tanPLWA (otd) = Starisord 44APLG L, mite
>0.40 For 25s = P: No Theran, Limite nenitor.no Requ, red H
H 0.4 4
g il3 g g g
<,..to-,r.
CL
~
For 25N = P < 30s: tanPFAC (P) = 0.53 + 0.01 (P - 30s) y9 g
.O. m...
~Hl 0.2 -
WPFAC (p) = 0.40 + 0.01 (P - 305)
~.--.P.
04 q
^
For 30N < P: mPFAC (P) = 0.84 + 0.004143 (P - 100t0 N
og og O
- -3 WN I
I l
I l
I l
I 0.0 H
O hh ph O
10 20 30 40 50 60 70 80 90 100 POWER (% Rated)
"w u
M e t*
P 4uN
(,1 u
O L: l 1
,r
.I U !r I
a 9
fao Fn g()".
gUH p aO 8D r Wh mT0 oh.*tu5 4
uww Rn. 8.n#gFUN egB g= 2D wNe o'
w.t t
a*
%MO M"
poi dM EgM bM # 5$H tH qgo ~ 4 g
gg g gu w
u3 O@H gp]n>s
".n*P Hm gHC f"
gh hM 9
o g
1 gHU *H HU N U ohg 4 yO Q"
gQ 8
0 1
1
)
d s
0 t
it s
r I
0 m
e 1
(
i w
R L
o G
R l
H n O s
L o
P t
, i 5
mP L
fB r
0 I
90 0
e 4
7 m+ev a
d 1
0 n
1
)
d 0
h 4
a c
F r
0 i
w
=
0
(
a 1
h d
/
O n c w lo w
=
A a
W F
l f
1 0
o 8
F t
F B
P s a e
W 0
r e
=
f o
r 1
A C
o
=
)
C d
=
=
d 0
)
t e m 7
l 7 )
F a
)
t u
2
(
C F
m m
8 d
(
A i
5 e
R R
x G G C
M i
0 t
e N
t A
n a
L L
F
=
=
R P
P P
r l
0 W mm w
F A
e o
f 6
(
W O
1 0 L 5
F E
RO 0 C 1
4 0
I 3
0 1
2 m
4 o
0 1
~
0 0
9 1
0 7,
6 5
g g
O 0
o 1u gC a& 8FQ
- r ag g
l
m.
s' t* 4
~
uW NO wo g
9 m
NO
- M 3.0 H
g "Q
$9 v M OPERATipG L8MIT MCMt (P) = kb a OPERATipG LlulT MCPR (100) q g
For P = 2S; #G TEftsAL LautTS OITERipG REDutRED Q
lHl (T.
ado LinstTS SPECIF8ED hH 2.6
' 2.63 Fce em s a.
e (sbypass = 3aso:
p
>60K Fim opp),,3y,, o g3. g 3o,, p)
Ebyp = 2.21 For s $35 Core Flow p.a. m n
k 58 g *. 2.4 2.36, 2.esFor em nr.Flo.
gQ 4
aw Qg N
For 30s s P = 4M:
Ep = 1.29 + 0.0134 (4m - PJ 3p 2.2 g p,_f
'2.21 For 4 3 g P. BGE:
Kp = 1.15 + 0.00367 (50s - P) t*
g
@g I
For em s P:
rp = 1 O + 0,00MS (1005 - P)
QQ W$
O OO 2.0 H
M >^-
64 h
ABSOLUTE 8
NN O a
On@G n
MULTIPLIER o
m n
,4 H g
1.s y
{k1.1
, 1.4s E
$= $
"Eo
$f 1.2e N
E I
.2 i.15 pHg 1
gu H
44 g
g
$y 0f 1
1 l
l l
l l
j g
3,n 4
0 10 20 30 40 50 60 70 80 90 100 g*E h
POWER (% rated')
H Os m
u O t*
- w AuMw M
h 4
t* 4 MM NO WO g
M4
&E d4i MO 8H 3.6 EH O
3.55 HQ g"S "hD g.
3.4 MN$
N g".Hl 32 3.2
- 6...
3.24
_,.<,..-<P,.._,.s.<,.,,_<,=
W.
UM Fw P = 25s: 80 TEste4L LiutTS tONt,ERING REQUIRED 3.0 so Leusis sPECtFIED p
HM M
Ol,2.a to g
F, 25m s p. myp.
cmyp...
3 so:
mn = sbyp. D.052
- C305 - PJ g
W tr w 2.67
@ k 2.6 a 3.24 Fr = 50s core Flow H.
O
- W 3
U o)
U WS
" 2.4 For 305 s P e 455:
Kp = 1. 29 + 0. 0134 (4SE - P) gq g
M 1 60E Flow
,2.36 Ogg g
For 455 s P e 805:
Ep = 1.15 - 0.00957 (605 - P) 2.2 rw ses s P:
Kp. 1.o. o 00375 (toom - P3 Q
(t 4 Q
W N
83 O
M W
n 2.0 H$Hlm y
v
_ ABSOLUTE
_ MULTIPLIER lNO 85 1.6 D1 0
g 7
3 2,1.4 M
a U
a)
N ~ 1.2 1.28 sH
@$g 1.is 44 3
gp 8
j l
1 l
I I
I I
g i
3,o gy4 0f 0
10 20 30 40 50 60 70 80 90 100 yQ POWER (% rated)
@E H
. " =
'h w
W:
Oca
.w 4NNw q
I t
1 4
f m
i pn Mo WO g
H OE m
OC.
l NO 2.0 4
8 t-*
For Wc (X Rated Core Flow) < 405 H
8
{l MCPR CF) = CAfwc/100+Bf) g g
1.s3
[1 + 0.0032 C40 - We))
g
- n n
1.s a
9 M
H l
E EM3 ps l
g l8 l
For We CX Rated Core Flow) 3 40 %
p 1.7 8
MCPR CF) = AfWc/100 + Bf, OR 1.23; a
m p
N m" r whichever is Oreater OH a
6
%U y
a e
Hh f$
HO C 1.8 i.s?
q gg U
For unx Core Flow = 114.OM:
g g
v i
tr l
Af = -0.639 dP 84 4kE kr OO
=1 GM "h.
O
.5 l
l
- O Bf = 1.026 O *4 glo u
n e
M h
?
8 1.4 8
8 K
e O
H
+
e 4
8 i
m H
e t
13 l
l l
a@
gHE9 K
i i
1.22 Ea" 1.2 l
l g
4 y
8" l
l l
t mm p
9N e
l I
l 1
1 1
l 1 i.
l AO i
g 3,3 Q
gO
- i o
10 20 30 40 50 so 70 so so "'"
100 11o I
CORE FLOW (% rated) y wO O
h M
We O t*
- w
<p N
W e:
H
+.
r_ag,me,m o
l PSCO Nuc10Cr, pug 1 & SOrvicOO Divicicn PCCO-COLR-L2R3 L2R3 Core Operating Limits Report Page 33, Rev. 1 TABLE 1 ROD BLOCK MONITOR SETPOINTS Nominal Trip Allowable Value setpoint LTSP 117.1%
118.3%
ITSP 112.3%
113.5%
HTSP 107.3%
108.5%
DTSP 92%
89%
l l These setpoints are based on a MCPR limit of 1.28 and are consistent with a RBM filter time constant between 0.1 seconds and 0.55 seconds.
'j*.
PECO En rgy, Puol is Services Division PECO-COLR-L2R3 L2R3 Core Operating Limits Report Page.34, Rev. O i
l m
TABLE 2 MAPLHGR SINGLE LOOP OPERATION (SL3) REDUCTION FACTOR i
i SLO reduction factor = 1.00 for t.ll cycle 4 fuel types.
j l
~
~
{
,f,
i
- PZCD Energy, FuS1 & SOrvices Division PECO-COLR-L2R3 L2R3 Core Operating Limits Report Page 35, Rev. 0 l
l i
e TABLE 3 l
LINEAR HEAT GENERATION RATE LIMITS i
FUEL TYPE MAXIMUM VALUE 1
GE6 13.4 kW/ft GE9B 14.4 kW/ft Gell 14.4 kW/ft ABB SVEA-96 (QFB) 17.7 kW/ft i
y '# e
?
PECD Energy, Fuol & S rvicoc Division PECO-COLR-L2R3 L2R3 Core Operating Limits Report Page 36, Rev. O TABLE 4 TURBINE BYPASS VALVE PARAMETE*.S TURBINE BYPASS SYSTEM RESPONSE TIME Maximum delay time before 0.10 sec start of bypass valve opening following generation of the turbine bypass valve flow j
signal Maximum time after generation 0.30 sec of a turbine bypass valve flow signal for bypass valve position to reach 80% of full stroke (includes the above delay time)
MINIMUM REOUIRED BYPASS VALVES TO MAINTAIN SYSTEM OPERABILITY l
l Number of valves = 7
.._,s.
d*t, 'e.
l PECO NuclCOr, Fuol'& ScrvicOc Divicion PECO-COLR-L2R3 L2R3 Core Operating Limits Report Page 37, Rev. 1 1
.I TABLE 5 l
Recirculation Pump Motor-Generator (MG) Set Scoop Tube Stops Mechanical 5 114%
Electrical 5 112%
TABLE 6 Cortrol Rod Block Instrumentation Reactor Coolant System Recirculation Flow Upscale Trip Nominal Trip Setpoint 5 113.4%
Allowable Value 5 115.6%
,