ML20135C690
| ML20135C690 | |
| Person / Time | |
|---|---|
| Site: | Limerick  |
| Issue date: | 01/22/1997 |
| From: | Hoffman C, Mchale J, Tusar J PECO ENERGY CO., (FORMERLY PHILADELPHIA ELECTRIC |
| To: | |
| Shared Package | |
| ML20135C658 | List: |
| References | |
| PECO-COLR-L2R4, PECO-COLR-L2R4-R, PECO-COLR-L2R4-R00, NUDOCS 9703040216 | |
| Download: ML20135C690 (24) | |
Text
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P'lCO NuclOOr, Fuol & Sgrvicca DiviDion PECO-COLR-L2R4
.L2R4 Core Operating Limits Report Page 1, Rev. 0 i
CORE OPERATING LIMITS REPORT FOR l LIMERICK GENERATING STATION UNIT 2 ;
l RELOAD 4, CYCLE 5 I Prepared By: A. bNA A Date: I, 33 C/7 j J. La. McHale '
Engineer Reviewed By: . .
M Date: /[2 L/4 h i
- 8. Tusar I '
//
Mnde ndent Reviewer Reviewed By: "
! Date: //22./f 7 C'. K. Hofifnan Independent Reviewer i
/
Date: 2 2[p 7 Approved By:~V J. M. Carmddy Manager Nuclear Design & Materials Branch 9703040216 970225 PDR ADOCK 05000353 p PDR
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PECO Nucler_r, Fu31 & S:;rvicO3 Divicion PECO-COLR-L2R4
. L2R4 Core Operating Limits Report Page 2, Rev. 0 e
LIST OF EFFECTIVE PAGES l
L Page(s) Revision l 1-24 0 i
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PECO NuclOcr, Fuol & SOrvicOc Divicion PECO-COLR-L2R4
- L2R4 Core Operating Limits Report Page 3, Rev. 0 INTRODUCTION AND
SUMMARY
l j This report provides the following cycle-specific parameter limits
- for Limerick Generating Station Unit 2 Cycle 5:
- Maximum Average Planar Linear Heat Generation Rate (MAPLHGR)
- Minimum Critical Power Ratio (MCPR)
- Rod Block Monitor (RBM) data
- Linear Heat Generation Rate (LHGR) j l
- Turbine Bypass Valve parameters l
. Stops
- Reactor Coolant System Recirculation Flow Upscale Trips These values have been determined using NRC-approved methodology and are established such that all applicable limits of the plant safety analysis are met.
4 This report is submitted in accordance with Technical Specification 6.9.1.9 of Reference 1. Preparation of this report was performed 3 in accordance with PECO Nuclear, Fuel & Services Division Procedure FM-300. l The data presented in this report is valid for all points and i domains on the operating map, including: i
- Maximum Extended Load Line Limit (MELLL) down to 81% of 1 rated core flow during full power operation l
- Increased Core Flow (ICF) up to 110% of rated core flow
- Feedwater Heater Out of Service (FWHOOS) up to 60 F feedwater temperature reduction at any time during the ,
1 cycle prior to cycle extension.
1 MAPLHGR LIMITS The limiting MAPLHGR value for the most limiting lattice (excluding natural uranium) of each fuel type as a function of average planar exposure is given in Figures 1 through 6. 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 3).
PECO Nuclear, Fuol & S&rviccc Division PECO-COLR-L2R4
. L2R4 Coro Op3 rating Limito R port Page 4, Rev. 0 MCPR LIMITS The MCPR value for use in Technical Specification 3.2.3 for each fuel type is given in Table 1. This table is valid for all Cycle 5 fuel types and operating domains. Information regarding the treatment of these MCPR limits for SLO is also provided.
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 (EOOS) condition.
Note that in Table 1 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 l begins). The cycle exposure which represents " EOR" is given in the I latest verified and approved Cycle Management Report. This value can change during the cycle due to changes in operating strategy. j i
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 sufficiently generic to apply to all fuel types and ,
operating domains. However, there are two sets of power-dependent l MAPLHGR multipliers for with- and without-EOOS conditions. Also, l there are two sets of power-dependent MCPR adjustments and j multipliers for with- and without-EOOS conditions. 1 These adjustments and multipliers are shown in Figures 7 through 12. Thermal limit monitoring must be performed with the j more limiting MCPR and MAPLHGR limits resulting from the power- and !
flow-biased calculation.
ROD BLOCK MONITOR SETPOINTS The ARTS RBM provides for power-dependent RBM trips. The trip setpoints/ allowable values and applicable RBM signal filter time constant data are shown in Table 2.
LINEAR HEAT GENERATION RATES The maximum LHGR value for each fuel type for use in Technical j Specification 3.2.4 is given in Table 4. The LHGR is an exposure j dependent value. Due to the proprietary nature of these values only the maximum LHGR for each fuel type is listed in Table 4. The LHGR data is listed in Reference 3 (GE proprietary).
l
d PECO NuclOOr, FuO1 & S rvicOc Divicion PECO-COLR-L2R4
. L2R4 Cora Operc. ting Limito Report Page 5, Rev. O j STEAM BYPASS SYSTEM OPERABILITY The operability requirements for the steam bypass system for use in Technical Specifications 3.7.8 and 4.7.8.C are found in Table 5. If these requirements cannot be met, the MCPR, MCPR(P) I and MAPFAC(P) limits for inoperable Steam Bypass System, known as Turbine Bypass Valve Out Of Service (TBVOOS), must be used.
RECIRCULATION PUMP ' RIP OPERABILITY l If the recirculation pump trip is inoperable, then the MCPR, MCPRlP) and MAPFAC(P) limits for Recirculation Pump Trip Out Of i Service (RPTOOS), must be used.
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RECIRCULATION PUMP MOTOR-GENERATOR (MG) SET SCOOP TUBE STOPS The electrical and mechanical stops are set to limit the j reactor core coolant flow rate during an event in which the recirculation flow rate increases to its maximum value. Technical i Specification Surveillance Requirement number 4.4.1.1.2 requires that each pump MG set scoop tube mechanical and electrical stop shall be demonstrated OPERABLE, with overspeed setpoints less than or equal to specified values, at least once per 24 months. The settings of these stops may be changed during the cycle in accordance with changes in operational strategy. These values are cycle-specific and can be found in Table 6 of this COLR.
CONTROL ROD BLOCK INSTRUMENTATION REACTOR COOLANT SYSTEM RECIRCULATION FLOW UFSCALE TRIP Technical Specification Limiting Condition for Operation number 3.3.6 requires control rod block instrumentation channels shall be OPERABLE with their trip setpoints consistent with the values shown in the 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 7 of this COLR. Table 7 lists the Nominal Trip Setpoint and Allowable Value. These setpoints are set high enough to allow full utilization of the enhanced ICF domain up to 110% of rated core flow.
DEBRIS FILTER BUNDLES Limerick Unit 2 Cycle 5 is the second cycle of irradiation for a GE Fuel Bundle fitted with a debris-resistant lower tie plate (LTP). Four of the Reload 3 Gell fuel bundles are equipped with these debris-resistant LTPs. The debris filter bundles are 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 Reference 8.
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PECO Nuc1 Car, Fual & S;rvicOc Divicion PECO-COLR-L2R4
. L2R4 Cora OperOting Limito Report Page 6, Rev. 0 SAFETY LIMIT MINIMUM CRITICAL POWER RATIO (SLMCPR)
The Safety Limit Minimum Critical Power Ration (SLMCPR) for Limerick 2 Cycle 5 is . 1.11 for Dual Loop Operation and 1.12 for Single Loop Operation. These values are documented in Reference 2.
REFERENCES 1.~" Technical Specifications and Bases for Limerick Generating Station Unit 2", Docket No. 50-353, License No. NPF-85.
- 2. " Supplemental Reload Licensing Report for Limerick Generating Station Unit 2 Reload 4 Cycle 5", General Electric Company Document No. 24A5383, Rev. O, January 1997.
- 3. " Lattice Dependent MAPLHGR Report for Limerick Generating Station Unit 2 Reload 4 Cycle 5", General Electric Company Document No. 24A5383AA, Rev. O, January 1997.
- 4. " Lattice Dependent MAPLHGR Report for Limerick Generating Station Unit 2 Reload 3 Cycle 4", General Electric Company Document No. 24A5168AA, Rev. O, January 1995.
- 5. " Lattice-Dependent MAPLHGR Report for Limerick Generating Station Unit 2 Reload 2 Cycle 3", General Electric Company Document No. 23A7200AA, Rev. 3, July 1994.
- 6. Letter, G. V. Kumar to K. M. McGinnis, " Limerick ARTS ,
Application with Equipment Out-of-Service (EOOS)", Dec. 10, 1993. l
- 7. " Safety Review for Limerick Generating Station Units 1 and 2, 110% Increased Core Flow Operation and Final Feedwater I Temperature Reduction", GE Nuclear Energy Document No. NEDC- l 32224P, Revision 1, October 1994. I
LG 94-11314.
- 9. " 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.
( 10. "GE NSSS Setpoints Required to Support Power Rerate", PECON i
Calculation No. LE-0082, July 27,1995.
- 11. Letter, R. M. Butrovich to H. J. Diamond, " Limerick 2 Cycle 5 ARTS Thermal Limits Curves", December 4, 1996.
- 12. Letter, R. M. Butrovich to J. M. Carmody, " Limerick 2 Cycle 5 Resolved OPL-3 and Revised FRED Form", September 13, 1996.
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PECO Nuc100r, Fuci & SOrvicO3 Division PECO-COLR-L2R4
. L2R4 Cora Op3 rating LimitD R port Page 7, Rev. 0 i
Figure 1 1 MAXIMUM AVERAGE PLANAR LINEAR HEAT GENERATION RATE (MAPLHGR)
VERSUS AVERAGE PLANAR EXPOSURE FUEL TYPE P9 CUB 331-9GZ (GE11-LGS 1 Reinsert)
Thi.1 Figure is Referred to by Technical Specification 3.2.1
- s. . .
u... . .. . . ' . . . .. 4.. '.
.-.............l.... ..... ........
u...
_u... . .
.-.- . e.... -- . -
2 ac . . .
~,.... . .. . ....... .... ...... . ............ . . ....
g . . . .
5 : : :
- a .
g . .. . . . . . . . . . .. .. . ......,. .. .
j . . . . .
,... .... ...;............ ....;.... ... .; . . . .....} . . .
4 . . . . .
... 1
... 2... n.. n.. .... u.. .... i Average Planar Exposure (GWd/ST) l l
l Avg. Plan Avg. Plan Avg. Plan Exposure MAPLHGR Exposure MAPLHGR Exposure MAPLHGR (GWd/ST) (kW/ft) (GWd/ST) (kW/ft) (GWd/ST) (kW/ft) 0.0 11.76 7.0 12.40 25.0 11.17 0.2 11.80 8.0 12.49 30.0 10.57 1 1.0 11.89 9.0 12.58 35.0 9.95
, 2.0 12.01 10.0 12.67 40.0 9.30 3.0 12.08 12.5 12.67 45.0 8.62 4.0 12.16 15.0 12.39 50.0 7.90 5.0 12.24 17.5 12.08 55.0 7.16 6.0 12.32 20.0 11.77 58.67 6.52
PECO NuclCOr, Fuoi & S rvic33 Division PECO-COLR-L2R4
. L2R4 Coro Opers. ting Limito Report Page 8, Rev. 0 4
Figure 2 4
MAXIMUM AVERAGE PLANAR LINEAR HEAT GENERATION RATE (MAPLHGR)
- VERSUS AVERAGE PLANAR EXPOSURE l FUEL TYPE P9 CUB 354-12GZ2 (Gell)
This Figure is Referred to by Technical Specification 3.2.1 u..
4 4
n... ..
3 n... .. .. ..
_ u .. i .. . . . . . .. ......, . . . .. . . .... ... .i .. . .
g . . . . .
y . . .
as . . .
- 1. . . . .. . . .. . .. ... ... .. .. . .. ........... . . ...
5 a
g . .. . . . . . . . :. . . . . ...'..
... n. . . a... >... .... .... ....
Average Planar Exposure (GWd/ST)
Avg. Plan Avg. Plan Avg. Plan Exposure MAPLHGR Exposure MAPLHGR Exposure MAPLHGR (GWd/ST) (kW/ft) (GWd/ST) (kW/ft) (GWd/ST) (kW/ft) 0.0 11.05 7.0 11.98 25.0 10.89 0.2 11.09 8.0 12.13 30.0 10.27 1.0 11.19 9.0 12.30 35.0 9.55 2.0 11.31 10.0 12.42 40.0 8.87 3.0 11.44 12.5 12.38 45.0 8.24 4.0 11.56 15.0 12.10 50.0 7.62 5.0 11.70 17.5 11.79 55.0 7.00 6.0 11.84 20.0 11.49 57.9 6.60 l
4 PECO Nuc1 gor, Puol & SOrvic33 Divicion PECO-COLR-L2R4 L2R4 Cora Op3r2 ting Limits Report Pags 9, Rsv. 0 Figure 3 MAXIMUM AVERAGE PLANAR LINEAR HEAT GENERATION RATE (MAPLHGR)
VERSUS AVERAGE PLANAR EXPOSURE FUEL TYPE P9 CUB 399-14GZ (Gell)
This Figure is Referred to by Technical Specification 3.2.1
- 1. . .
u... .. .... .; . . . .;.. ... . . :. . . . . . ' . . ......;. .. .
u... ......
.{. ... .. ....... .; ... . . ;... ..
F- <
g . . . . .
s.... .
g1 . . . .
3 . . . . .
...q .. ... . ....
, .:.... ... 3 .. . .
Average Planar Exposure (GWd/ST)
Avg. Plan Avg. Plan Avg. Plan Exposure MAPLHGR Exposure MAPLHGR Exposure MAPLHGR (GWd/ST) (kW/ft) (GWd/ST) (kW/ft) (GWd/ST) (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 1
5.0 11.38 17.5 11.68 55.0 6.90 j 6.0 11.53 20.0 11.37 57.1 6.59 I
l
. .- . ..-. . - . _ .~ _ - - . . _ _ - . _ _ _ - . ~ . . ~ .. . . . _ . . _ -
d j
PECO Nuclocr, Fuol & S rvicOS Diviolon PECO-COLR-L2R4
. L2R4 Coro Op0 rating Limits R port Page 10, Rev. 0 J Figure 4 MAXIMUM AVERAGE PLANAR LINEAR HEAT GENERATION RATE (MAPLHGR)
VERSUS AVERAGE PLANAR EXPOSURE FUEL TYPE P8CIB219-4GZ (GE6) i
. This Figure is Referred to by Technical Specification 3.2.1 !
i :
i 1,.. .- - - !
, 13... .. ..
...;. .. ..j.. . . . . . .. . ......;........ . .. ..
ns.. . - - - - - - - -- . .. . . .. .. ..
y . . .
7 g .
.w . . . .
J 11..- - - * - - - * * '- -- ***-- * - - ' * ----* * - * - + ---** ** **-- *
~
g . . .
5 S
? . . . . ,
I . . . .
1,...
... .. ..: . ......q... . .
g.... . . . . . . . . ... . . . . 3 . . .....r ... ......... . ., . ... .
4 s . . >
- 1. . .
... ... n. . . 1... .... , , - ,...
Average Planar Exposure (GW4/ST) l i
i 1
1 1
Avg. Plan Avg. Plan Avg. Plan '
Exposure MAPLHGR Exposure MAPLHGR Exposure MAPLHGR (GWd/ST) (GWd/ST) (GWd/ST)
(kW/ft) (kW/ft) (kW/ft) 0.2 11.90 10.0 11.90 25.0 11.60 i 1.0 11.90 15.0 11.90 30.0 11.20 5.0 12.00 20.0 11.80 i
4 4
i
4 PECO Nuclocr, Fu31 & S2rvicOc Division PECO-COLR-L2R4 L2R4 Coro OperOting Limits Report Page 11, Rev. 0 Figure 5 MAXIMUM AVERAGE PLANAR LINEAR HEAT GENERATION RATE (MAPLHGR)
VERSUS AVERAGE PLANAR EXPOSURE FUEL TYPE P8CIB176-4GZ (GE6)
This Figure is Referred to by Technical Specification 3.2.1 u.. - ~ . - -
12.S
/ .
u.. l g : . .
z . . .
.I : : : . .
~ u.i g . . . . .
5 a
I : : l l u..
.... l i... .
... ... i... 1... 2... a. . . ....
Aveerage Planar Exposure (CWd/ST) i l
Avg. Plan Avg. Plan Avg. Plan Exposure MAPLHGR Exposure MAPLHGR Exposure MAPLHGR (GWd/ST) (kW/ft) (GWd/ST) (kW/ft) (GWd/ST) (kW/ft) 0.2 11.80 10.0 12.00 25.0 11.70 1.0 11.90 15.0 12.00 30.0 10.80 5.0 12.00 20.0 11.90 1
1 P3CO Nuc1c2r, Fu^.,1 & S rvicOG Divi 0 ion PECO-COLR-L2R4 L2R4 Cara OperOting Limito Report Page 12, Rev. 0 1
1 Figure 6 l MAXIMUM AVERAGE PLANAR LINEAR HEAT GENERATION RATE (MAPLHGR)
VERSUS AVERAGE PLANAR EXPOSURE FUEL TYPE P9CTB416-15GZ (GE13)
This Figure is Referred to by Technical Specification 3.2.1 2
i...
4
, u... . .. .....
... s..... , , .., . .. .
j u... ....
.,. .. 4 .... . .; .. . ..;.... . . . . ;. ... . .
.. ........ . s... . . . . ... .... .. . ... ..s . ... .
., u . . . . . . .
t ,
, 3 . . . .
u... ... ........... ...... . .. . .. . . . . . . ... .... .. I g . .
g . . . . .
. . . . \
d . .. . .... . . . . . ........ . .. .. . . . .. ......... . .
, i . . . .
,... . .. ;... ....{... ....;.. .... , ........} .. ..
... i... .... .... .... .... ....
Average Planar Exposure (GWd/ST)
Avg. Plan Avg. Plan Avg. Plan Exposure MAPLHGR Exposure MAPLHGR Exposure MAPLHGR (GWd/ST) (kW/ft) (GWd/ST) (kW/ft) (GWd/ST) (kW/ft1 0.0 10.54 7.0 11.76 25.0 10.99 0.2 10.60 8.0 11.91 30.0 10.36 1.0 10.73 9.0 12.04 35.0 9.74 2.0 10.90 10.0 12.16 40.0 9.11 3.0 11.09 12.5 12.18 45.0 8.46 4.0 11.3' 15.0 12.11 50.0 7.78 5.0 11. C 17.5 11.91 55.0 7.08 6.0 11.d1 20.0 11.62 58.05 6.63
PECO NuclOOr, FuOl & S rvic 3 Divicion PECO-COLR-L2R4 L2R4 Cara Operating Limits Report Page 13, Rev. 0 FIGURE 7 l POWER DEPENDENT MAPLHGR MULTIPLIER MAPFAC(P)
THIS FIGURE IS VALID FOR THE RCF, ICF, MRTTT, FWHOOS AND FWTR OPERATING DOMAINS This Figure is Referred to by Technical Specificatien 3.2.1 s .. - - -
1 e .. .
l l
E y e .. .
15 I .. .
. 0.63 g <= 60% Flow g,,,, , MAPLHGR(P) = MAPF AC(P)
- MAPLNGRstd a
0.55 MAPLHGRstd = Standard MAPLHGR Umits h'
g O.48 ;
.50 For 25% > P : No Thermal Umsts Monitoring Reqdred No umits Speatied E l l
, e .e . l l For 25% <= P < 30% ; MAPFAC(P) = 0.55 + 0.004(P 30%)
g > 60% Flo" '
j For <= 60% Core Flow 1gs.: . , ; MAPFAC(P) = 0.50 + 0.004(P . 30%)
For > 60% Care Flow k ,,,. l l For 30% <= P : MAPFAC(P) =1.0+ 0.005224(P.100%) i a : :
e.s . { {
l l l s.e e se se so se se se is se se too Power (4 Rated) l
PECO NuclCCr, Fuol & S rvicOO Divicicn PECO-COLR-L2R4
- L2R4 COro Oper ting Limito Report Page 14, Rev. 0 FIGURE 8 POWER DEPENDENT MAPLHGR MULTIPLIER MAPFAC(P)
THIS FIGURE IS VALID FOR THE RPTOOS AND/OR TBVOOS OPERATING DOMAINS
, This Figure is Referred to by Technical Specification 3.2.1 1
.i
..s.
E g . .. .
I 3 e., .
i t o.s .
- c. 60% Flow 0.55 E MAPLHGR(P) = MAPFAC(P)
- MAPLnedsta
- 4 0.53 o e ,a . MAPLH3Rstd = Standard MAPLHGR Umsts 3 0.48 :
{ { For 25% > P : No Thermal Umits Monitanng Required
,,,, ; ' O.40 No umits Specified 0.35 For 25% c. P < 30% : MAPFAC(P) = 0.53 + 0.01(P - 30%)
{ . > 60% Flow For <= 60% Core Flow 3 ; ; MAPFAC(P) =0.40 + 0.01(P - 30%) )
- ; For > 60% Care Flow
,, o.a . ; ;
For 30% <= P : MAPFAC(P) = 0.84+ 0.004143(P 100%)
e.a . j j l
- s.e a to se se se se so to se se see Power (% Rated) l l
l 2
l l
P"CO NuclOcr, Fuol te SOrvicos Divicion PECO-COLR-L2R4 L2R4 Ccra OperOting Limito R port Page 15, Rev. 0 FIGURE 9 FLOW DEPENDENT MAPLHGR MULTIPLIER MAPFAC(F) 4 THIS FIGURE IS VALID FOR ALL OPERATING DOMAINS l
- i This Figure is Referred to by Technical Specification 3.2.1 i i 1 !
34 4
s .. .
j
= i b....
j M i I MAX FLOW.100%
$ MAX. FLOW = 114% i a 1
$ MAPLHGR(F) . MAPFACf
- MAPLHGRstd I b
i e .7 MAPLHGRstd . STANDARD MAPLHGR LIMITS b
MAPFACf(F; . MINIMUM (1.0, Af
- We /100 + Bf) a:
h / We. % RATED CORE FLOW g e.s.
l
- AND Af Bf ARE CONSTANTS GIVEN BELOW
4 R ]
MAX. CORE FLOW (% RATED) Af Bf 109.0 0.6773 0.4430 l 4 ,,,. 114.0 0.6827 0.4070 e .s to se ao se so so to so ** too ***
Core Flow (% Rated) s
.. . . - = - _ . _ - . . . - . - . _ - ... .. - . . . . - . . . . . _ _ - . _ -
PECO Nuc1 car, FuG1 & S0rvicO3 Division PECO-COLR-L2R4
- L2R4 Coro OperOting Limits Report Page 16, Rev. O r
TABLE 1 .
OPERATING LIMIT MINIMUM CRITICAL POWER RATIO (OLMCPR) i Use in conjunction with Figures 10, 11 and 12.
- This table is valid for two-loop operation.
- Add 0.01 to the OLMCPR when in Single Loop Operation.
- This table is valid for all Cycle 5 fuel types.
J
- This table is referred to by Technical Specification 3.2.3.
1 i
i TBV In Service TBV Out of RPT Out of
, and Service Service RPT In Service i.
f Opt. B Opt. A Opt. B Opt. A Opt. B Opt. A j (Tau =0) (Tau =1) (Tau =0) (Tau =1) (Tau =0) (Tau =1) i
- BOC TO EOR - 1.30 1.33 1.37 1.40 1.37 1.42 1 l 2000 )
mwd /ST l ,
EOR -
2000 1.34 1.37 1.39 1.42 1.40 1.48 mwd /ST !
to EOC l
Notes:
- 1. When Tau does not equal 0 or 1, detennine OLMCPR via linear interpolation.
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PECO Nuclocr, Fuol & S:rvicOO Div10 ion PECO-COLR-L2R4 L2R4 Core Operating Limits Report Page 27, Rev. 0 l
I FIGURE 10 POWER DEPENDENT MCPR LIMIT ADJUSTMENTS AND MULTIPLIF.RS I
, THIS FIGURE IS VALID FOR THE RCF, ICF, MELLL, FWHOOS i AND FWTR OPERATING DOMAINS l l
This Figure is Referred to by Technical Specification 3.2.3 U I
. i s...- - - -- - -
l
~3,., 2.80 OPERATING LIMIT MCPR(P) = Kp
- OPERATING LIMIT MCPR(100)
".'. ; W > 60% Flow
@ { FOR P<25% : NO THERMAL LIMIT MONITORING REOUIRED 3,,,
, 2.65 NO LIMITS SPECIFIED j 0
i ! ! FOR 25% <= P < Pbypass :(Pbypass = 30%) 1 2.39 I a .4 - <= 60% Flow Kp = [ Kbyp + 0 030(30% P)} / OLMCPR(100) 5 Kbyp = 2.24 FOR <= 60% CORE FLOW
" a .: < 2 24 = 2.65 FOR > 60% CORE FLOW
{
8 : :
- l : FOR 30% <= P < 45% ; Kp = 1.28 + 0.0134(45%. P)
FOR 45% <= P < 60% : Kp = 1.15 + 0.00867(60%- P) h {
y ,,, , { : FOR 60% <= P : Kp = 1.00 + 0.00375(100% P)
O A ! !
$ i.e . : :
E ! ! ]
@ i.e . :
g
- : I l ! !
g i .. . : :
1.s e se so as se se se to es e. too Power (% Rated) l i
w - - - - -
-A- -a __ 4 L_6-1 .
PECO NuclCOr, Fuol & S rvicOS Divicicn PECO-COLR-L2R4 L2R4 Coro Op3r ting Limit 0 Report Page 18, Rev. 0 FIGURE 11 4 POWER DEPENDENT MCPR LIMIT ADJUSTMENTS AND MULTIPLIERS THIS FIGURE IS VALID FOR THE RPTOOS AND/OR TBVOOS OPERATING DOMAINS This Figure is Referred to by Technical Specification 3.2.3 1
s.e l 3.58 OPERATING LIMIT MCPR(P) . Kp
- OPERATING (IMIT MCPR(100) g , g > 60% Flow FOR Pc25% : NO THERMAL LIMIT MONITORING REOUIRED i
-! ' ! NO LIMITS SPECIFIED
- 3.27 g { FOR 25% < P < Pbypass : (Pbypass = 30%)
' 3.e . I : Kp { Kbyp + 0.002(30% - P)] / OLMCPR(100) o : :
g ; l Kbyp 2.39 FOR <= 60% CORE FLOW
$ 2.70 = 3.27 FOR > 60% CORE FLOW
{
a.s ' '
<= 60% Flow FOR 30% <= P < 45% : Kp .1.28 + 0 0134(45%. P)
FOR 45% 4. P < 60% Kp .1.15 + 0.00867(60% . P) j , 2.39
~,,,, '
j FOR 60% c. P : Kp.1.00 + 0.00375(100% P) a : :
- 7. I i i : :
sc * '
l U ! ! d
= : .
g 1.s -
1.s e to as ao se se so to es se too Power (% Rated)
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1 1
1 l
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, i PECO Nucicar, Fuci & S rvicO3 DiviDion PECO-COLR-L2R4 L2R4 Coro Op3 rating Limito Report Page 19, Rev. 0 FIGURE 12 FLOW DEPENDENT MCPR LIMITS MCPR(F)
THIS FIGURE IS VALID FOR ALL OPERATING DOMAINS This Figure is Referred to by Technical Specification 3.2.3 s.se FOR We (% RATED CORE FLOW) < 40% FOR We (% RATED CORE FLOW) >= 40%
1 '
MCPR(F) = [(Af
- We /100 + Bf ' MCPR(F) = MAX (1.24. Af
- We/100 + Bf)
[1 + 0.0032(40 Wc)] 1.es - MAX FLOW f% of Rated) Af Rf 109.0 -0.615 1.781 114.0 -G.532 1.833 1.ts . {* MAXIMUM FLOW RATE = 114.0% 2.so . MAXIMUp, FLOW RATE = 109.0%
/
1.as . 1.as . 1.as 3 10 30 38 40 69 as 18 to 90 100 110 Core Flow (4 Rated) i 1 i I
._- . _ _ . . - . =-. . _ _. .. .. - -
l PECO NuclCar, Fu31 & S0rvicO3 Divicion PT,CO-COLR-L2R4 I L2R4 Cara Operating Limits Report Page 20, Rev. 0 TABLE 2 i 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% I These setpoints are based on a MCPR limit of 1.30 and are consistent with a RBM filter time constant between 0.1 seconds and 0.55 seconds. I j i
PECO NuclOOr, Fu 1 & S0rvicOc Divicion PECO-COLR-L2R4 , L2R4 Core Operating Limits Report Page 21, Rev. 0 TABLE 3 MAPLHGR SINGLE LOOP OPERATION (SLO) REDUCTION FACTOR SLO reduction factor = 1.00 for all Cycle 5 fuel types. i I
PECO Nuc100r, FuOl & S rvic D DiviDion PECO-COLR-L2R4 ; L2R4 Cora OperOting Limito Report Paga 22, rov. 0 TABLE 4 1 LINEAR HEAT GENERATION RATE LIMITS FUEL TYPE MAXIMUM VALUE GE6 13.4 kW/ft Gell 14.4 kW/ft GE13 14.4 kW/ft NOTE: The LHGR is an exposure dependent value. Due to the proprietary nature of these values only the maximum LHGR for each fuel type is listed in Table 4. The LHGR data is listed in Reference 3 (GE proprietary). I i 1
PECO NuclOOr, Fuol & S rvicOc Division PECO-COLR-L2R4 L2R4 Ccro Opnrating Limito Report Page 23, Rev. 0 1 TABLE 5 TURBINE BYPASS VALVE PARAMETERS TURBINE BYPASS SYSTEM RESPONSE TIME Maximum delay time before. start 0.10 sec of bypass valve opening following generation of the turbine bypass valve flow 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 Number of valves = 7
PECO NuclOOr, Fu31 & S rvic00 Divicion PECO-COLR-L2R4 L2R4 Coro Op2rOting Limita Rrport Page 24, Rev. 0 TABLE 6 Recirculation Pump Motor-Generator (MG) Set Scoop Tube Stops ! Mechanical 5 109% i Electrical 5 107% 4 i. j TABLE 7 3 Control Rod Block Instrumentation j Reactor Coolant System Recirculation Flow Upscale Trip 2 Nominal Trip Setpoint s 113.4% i Allowable Value $ 115.6% i i I t 4 4 f
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