ML20199E328

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Rev 2 to PECO-COLR-L2R4, COLR for Lgs,Unit 2,Reload 4,Cycle 5
ML20199E328
Person / Time
Site: Limerick Constellation icon.png
Issue date: 11/23/1998
From: Carmody J, Hoffman C, Mchale J
PECO ENERGY CO., (FORMERLY PHILADELPHIA ELECTRIC
To:
Shared Package
ML20199E319 List:
References
PECO-COLR-L2R4, PECO-COLR-L2R4-R02, PECO-COLR-L2R4-R2, NUDOCS 9901200382
Download: ML20199E328 (24)
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Text

"

i PECO Nuclear, Fuel & SrrvicCC Divicion PECO-COLR-L2R4 I

i l L2R4 Core Operating Limits Report Page 1, Rev. 2 i

J l

l CORE OPERATING LIMITS REPORT l l

FOR LTM DTCK GENERATING STATION UNIT 2 RELOAD 4, CYCLE 5 j

)

i Prepared By: A Date: 11 / / 9 / 9 6  :

C. K. HoffmapV )

Engineer '

Reviewed By:

J.~

h. h La. McHale Date:_Il a3198 J

pIndependentReviewer  :

Approved By

[ M Date: l'/bt.3/f#

J. M. Ca(mody Manager Nuclear Design & Materials Branch 9901200382 DR 990111

(

p ADOCK 05000353 PDR

[ PECO Nuclear, FuOl & Cervices Divi = ion PECO-COLR-L2R4 i

. l L2R4 Core Operating Limits Report Page 2, Rev. 2

)

l-l l

t LIST OF EFFECTIVE PAGES I

(- Page(s) Revision l 1-24 2 i

l r

4 t

3

l PECO Nuclear, Fuel G Cervic 3 Divicion PECO-COLR-L2R4 l l L2R4 Core Operating Limits Report Page 3, Rev. 2 l INTRODUCTION AND

SUMMARY

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)

  • ARTS MCPR thermal limit adjustments and multipliers
  • MAPLHGR single loop operation (SLO) reduction factor )

Linear Heat Generation Rate (LHGR)

These values have been determined using NRC-approved methodology and are established such that all applicable limits of the plant l safety analysis are met.

l This n port is submitted in accordance with Technical Specification 6 . 9 .1. .- of Reference 1. Preparation of this report was performed in ar.srdance with PECO Nuclear, Fuel & Services Division Procedure FM-300.

The data presented in this report is valid for all points and domains on the operating map, including: l

  • 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 flow Feedwater Temperature Reduction (FWTR) up to 105 F during cycle extension operation
  • Feedwater Heater Out of Service (FWHOOS) up to 60 F feedwater temperature reduction at any time during the cycle prior to cycle extension.

N GR 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, Fuel & S rvicco Divicion PECO-COLR-L2R4 l L2R4 Core Operating Limits Report Page 4, Rev. 2 MCPR LIMITS The MCPR value for use in Technical Specification 3.2.3 for j each fuel type is given in Table 1. This table is valid for all  :

Cycle 5 fuel types and operating domains. Information regarding l 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 j begins). The cycle exposure which represents " EOR" is given in the l latest verified and approved Cycle Management Report. This value  !

can change during the cycle due to changes in operating strategy.

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 j MCPR (F) are sufficiently 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 7 through 12. Thermal limit monitoring must be performed with the 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 Specification 3.2.4 is given in Table 4. 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) .

l l

i

~

PECO Nuclear, Puol & Servicco Divicion PECO-COLR-L2R4 l L2R4 Core Operating Limits Report Page 5, Rev. 2 l

STEAM BYPASS SYSTEN 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) l and MAPFAC(P) limits for inoperable Steam Bypass System, known as i Turbine Bypass Valve Out Of Service (TBVOOS), must be used. '

l RECTRCL4ATION PUMP TRIP OPERABILITY '

If the recirculation pump trip is inoperable, then the MCPR, l MCPR(P) and MAPFAC(P) limits for Recirculation Pump Trip Out Of l Service (RPTOOS), must be used.

B3 CIRCULATION PUMP MOTOR-c m D1 TOR (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 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 Sisrr.d RECIRCUwf' ION FLOW UPSCALE 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 I values shown in the Trip Setpoint column of Technical Specification a Table 3.3.6-2. The Reactor Coolant System Recirculation Flow i Upscale Trip is a cycle-specific value and as such is found in I Table 7 of this COLR. Table 7 lists the Nominal Trip Setpoint and 1 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 BUND 74J Limerick Unit 2 Cycle 5 is the second cycle of irradiation for a GE Fuel Bundle fitted with a debris-resistant lower tie plate i

(LTP). Four of the Reload 3 Gell fuel bundles are equipped with these debris-resistant LTPs. The debris filter bundles are modeled l 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.

i PECO Nu31 ear, Fu 1 & Ccryicco Divicion PECO-COLR-L2R4 l L2R4 Core Operating Limits Report Page 6, Rev. 2 SAFETY LIMIT MINNM MTTICAL POlfER 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.

1

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.
7. " Safety Review for Limerick Generating Station Units 1 and 2, 110% Increased Core Flow Operation and Final Feedwater Temperature Reduction", GE Nuclear Energy Document No. NEDC-32224P, Revision 1, October 1994, i
8. "DEC for Use of GE-11 Debris Resistant Lower Tie Plate", ECR No. l LG 94-11314. l
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 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.
13. Letter, R. M. Butrovich to K. W. Hunt, " Assessment of Boron Injection at Limerick 2", June 6, 1998.

- -. . .. . - ._- .- . - ~ _ . - . . .- - - . . . . .

PECO Nuclear, Puel T S rvices Divicion PECO-COLR-L2R4 l L2R4 Core Operating Limits Report Page 7, Rev. 2 l

Figure 1 MAXIMt!M AVERAGE PLANAR LINEAR REAT GENERATION RATE (MAPLEGR)

VERSUS AVERAGE PLANAR EXPOSURE '

FUEL TYPE P9 CUB 331-9GZ (GE11-LGS 1 Reinsert)

This Figure is Referred to by Technical Specification 3.2.1 14.0 l  !

I i

23.0- t- --t '

t- - ~ -"'"

22.0; i

{!

n.0 - ** --

3 l l 20.0-

  • 4-

}

i 1

9.0

  • b' ~

i i

8.0 l '

i s

7.0' '

6.0 0.0 2D.0 20.0 30.0 40.0 50.0 60.0 Averego Planar Exposure (GBM/ST)

Avg. Plan Avg. Plan Avg. Plan l Exposure MAPLEGR Exposure MAPLEGR Exposure MAPLEGR l (GWd/ST) (kW/ft) (GWd/ST) (kW/ft) (GWd/ST) (kW/ft)

O0 11.76 7.0 12.40 25.0 11.17 0.2 11.80 8.0 12.49 30.0 10.57 l 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 12.33 20.0 11.77 58.67 6.52 l

~PECO Nuclear, Puel & S rvicca Divicion PECO-COLR-L2R4 l L2R4 Core Operating Limits Report Page 8, Rev. 2 1

Figure 2 l

MAXIMUM AVERAGE PLANAR LINEAR HEAT GENERATION RATE (MAPLEGR) I

, VERSUS AVERAGE PLANAR EXPOSURE l FUEL TYPE P9 CUB 354-12GZ2 (Gell) i This Figure is Referred to by Technical Specification 3.2.1 l

i 24.0 , . .

1 i

i l

i I i' i i

' i f 23.0 -

! l i

i 12.0- , i i

! i i i t 21.0'  ;  ;

j

= l  !

j 1 i l

l20.0- .

E  !  !

l  !

9.0 - 4 +

8.0 -

7 J"  ;

! . i

! a i .

l 7.0- 4-l t l

! l t

' t' 6.0 O.0 20.0 20.0 30.0 40.0 50.0 60.0 Average Planar P=w (Ged/ST)

Avg. Plan Avg. Plan Avg. Plan Exposure MAPLEGR Exposure MAPLEGR Exposure MAPLHGR (GWd/ST) (kW/ft) (GWd/ST) _(hW/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 l 2.0 11.31 10.0 12.42 40.0 8.87 l

3.0 11.44 12.5 12.38 45.0 8.24 4.0 11.56 15.0 12.10 50.0 7.62 i 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

+ . . . - . . - .. _ _ - -- -. . _ - - - . . . . . .

PECO Nuclear, Fuel & Cervicco Divicion PECO-COLR-L2R4 l L2R4 Core Operating Limits Report Page 9, Rev. 2 Figure 3  !

MAXIMUM AVERAGE PLANAR LINEAR HEAT GENERATION RATE (MAPLEGR)

VERSUS AVERAGE PLANAR EXPOSURE FUEL TYPE P9 CUB 399-14GZ (Gell)

This Figure is Referred to by Technical Specification 3.2.1 24.0  ;

I

~

4- '

23.0 +

22.0- t  ;

i 10- 4--

" 20.0 - + -' +

1 I

9.0 ' ' "

l s.O - +

7.0 t- '

1 i'

6.0 l 0.0 20.0 20.0 30.0 40.0 50.0 60.0

2. . -? Planar Pws (Ge$/ST)

Avg. Plan Avg. Plan Avg. Plan

Exposure MAPLEGR Exposure MAPLEGR Exposure MAPLEGR (GWd/ST) (kW/ft) (GWd/ST) (kW/f_t;). (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 l 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 l

1

. _ . _ . _ . _ _ . _ _ _ , _ . _ . . . ~ _ _ . _ _ . _ _ . _ _ . _ _ . . ___ _ _____. ._ - _ _ _ .

PECO Nuclear, Fuel O Cervicco Divicion PECO-COLR-L2R4 l l L2R4 Core Operating Limits Report Page 10, Rev. 2 ,

Figure 4 f

MAXIMON AVEItAGE PLANAR LINEnk EEAT GENERATION RATE (MAPLEGR)

VERSUS AVERAGE PLANAR EXPOSU3tB l' FUEL TYPE P8CIB219-4GE (GE6)

This Figure is Referred to by Technical Specification 3.2.1 l

23.0 L ,

f 22.5 t +  ;

i  !

l l i l j j l

1= c A '

f 5.

l l; " 21.5 - -& a - - +

4 -- --  !

I l

$ I l

f l 21.0 - t 6 a t

i l  !

20 3 - j- f-I 20.0

0.0 5.0 10.0 25.0 20.0 25.0 30.0 l Average Planar Exposure (Ged/ST) l l l l Avg. Plan Avg. Plan Avg. Plan {

! Exposure MAPLEGR Exposure MAPLEGR Exposure MAPLEGR  !

i (GWd/ST) (kW/ft) (GWd/ST) (kW/ft) (GWd/ST) (kW/ft) l O.2 11.90 10.0 11.90 25.0 11.60 1.0- 11.90 15.0 11.90 30.0 11.20 l 5.0 12.00 20.0 11.80 l

PECO Nuclear, Puol & Servicca Divicion PECO-COLR-L2R4

) L2R4 Core Operating Limits Report Page 11, Rev. 2 Figure 5 MAXIMOM AVERAGE PLANAR LINEAR HEAT GENERATION RATE (MAPLHGR)

VERSUS AVERAGE PLANAR RIPOSURE FDEL TYPE P8CIB176-4GZ (GE6)

This Figure is Referred to by Technical Specification 3.2.1  ;

23.0 t

1 i

12.5 .

1 i i i 12 0 3

u  : i It i,

5 i 5

h i: )

I 11.0 ,

N i

i  !

so.s  ;

i l l

i 20.0 0.0 5.0 10.0 25.0 20.0 25.0 30.0 Aveerage Planar Ekposure (Ged/ST)

Avg. Plan Avg. Plan Avg. Plan l Exposure MAPLEGR Exposure MAPLEGR Exposure MAPLEGR

_(gitd/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 t'

l

l PECO Nuclear, Fuel & ServicCJ Divi 0 ion PECO-COLR-L2R4 j i

l L2R4 Core Operating Limits Report , Page 12, Rev. 2 '

Figure 6 )

J MAEIMON AVERAGE PLANAR LINEAR HEAT GENERATION RATE (MAPLUGR)  ;

VERSUS AVenha PLAMAR EXPOSURE t FUEL TYPE P9CTB416-15GE (GE13) l l This Figure is Referred to by Technical Specification 3.2.1 24.0 i i 1  !  !

! i J 23.0 - W I

22.0 .

I 11.0- ----

4 ,

' ~~

E i i g < e i

20.0- t--  ;

I  ! j l i l  !

9.0 ~

l

{ i 8.0- "- 4 ~ '

l 7.0 - l ,

i

! I j

l; i i

i i '

l 6.0 1 0.0 20.0 20.0 30.0 40.0 50.0 60.0 l Average Planar rug-nu (G45/SD  !

Avg. Plan Avg. Plan Avg. Plan Exposure MAPLEGR Exposure MAPLEGR Exposure MAPLEGR )

(GWd/ST) (kW/ft) _[QWJfSR (kW/ft) (GWd/SR (kW/ft) 0.0 10.54 7.0 11.76 25.0 10.99 0.2 10.60 8.0 11.91 30.0 10.36 l 1.0 10.73 9.0 12.04 35.0 9.74 l

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 11.30 15.0 12.11 50.0 7.78 5.0 11.47 17.5 11.91 55.0 7.08 l 6.0 11.61 20.0 11.62 58.05 6.63 1

I i

. . . - ,- . =_ = -.

PECO Nuclear, Fuel & Servicca Divicion PECO-COLR-L2R4 l L2R4 Core Operating Limits Report Page 13, Rev. 2 l

, FIGURE 7 POWER DEPENDENT MAPLEGR MULTIPLIER MAPFAC(P) l TEIS FIGURE IS VALID FOR THE RCF, ICF, MELLL, FNHOOS AND

, FNTR OPERATING DCMAINS This Figure is Referred to by Technical Specification 3.2.1 i l

l i

1.0 0J-E g 0.8 -

f n

I 0.7 -

. Om g a M Row t0...  : weu<ne)=weFMe3 Weumia E

ass WPu<nad=SnkdWPLKRune g as .  :

5 Qe H "' For M> P: 2Thermd Umts Marmonry Regared a

I /

4: munasposed o 04' /::  : FcrMaP<3M: WPFMP)=Q55+0004(P-3mg e

l > 60%Ra* '

  • Fora 00%CoreRau

{o+0.3 -  : { WPFAQP)= 050+ 0.004(P-30%)

Far>00%Ctre Row k 0.2 - l  : For30%aP: WPFMP)= 1.0+ 00E24(P.1024) 1 0.1 - l  : 1 0.0 1

0 20 2) 30 40 50 60 70 80 90 100 Pcasar (% Rated) i 4

i PECO Nuclear, Fu21 & S::r.vicOD Divicion PECO-COLR-L2R4  !

l L2R4 C:r: Operating Lhits Report Page 14, Rev. 2 )

FIGURE 8 l

l POWER DEPENDENT MAPLEGR MULTIPLIER MAPFAC(P) )

THIS FIGURE IS VALID FOR THE RPTOOS AND/OR TBVOOS OPERATING DCBEAINS This Figure is Referred to by Technical Specification 3.2.1  ;

1.0 0.9 -

~

_ l b l u 0.8-f 0.7 -

)

C I

.o 1 g 0.6 ' = 60%Rm gg m.

nWUERP)= hMFFAQP)* MaPUCRed g ' 5' 4 5,

!m '**"*'""**"*

. De .  : I g l l For25%> P: 2 Thund Lines h4rstcrwg Recpred

, 0.4 - 0 40 ShW g  !.

.E 0.35 ; I. : Fcr 2S%c P < lD%: hMPFMP) = QS3 + Q O1(P- 3mq e 0.3,  :

> Rm kaMh Rw g . .

E l { MAPFNP)=040+0.01(P 30%)

k CJ- Ftr>00%Ctre Ron g . .

-b  :  : For30%a P:

  • McFFAQP)= 084 Q(D4143(P.100%)

Da- l  :

0.0 0 10 20 30 40 50 60 70 80 90 200 Power (% Rate 4 l

i l

1

! PECO Nuclear, Fu21 & Servic00 Divicien PECO-COLR-L2R4 j l L2R4 C;ra Operating Limits Report Page 15, Rev. 2 l FIGURE 9 FLOW DEPENDENT MAPLEGR MULTIPLIER MAPFAC(F)

THIS FIGURE IS VALID FOR ALL OPERATING DCEEAINS l' This Figure is Referred to by Technical Specification 3.2.1 i

l 1.1 l

1.0-E g 0.9 -

2 n

0.8 - b MM FlGV= 114%

E MARHRF)= M4FK2

  • M8PLKRad m

g 0.7 - M8ptMytad=STMO40MARXRUMTS c

MsFFACf(F)= MNMM(tQ N'M/100 + B) 8 3.0.6 a

Ma %MEMW

  1. 0#,9#ECCNiT#ESG\ENEELCW MM M PUWNMTM M N 10E0 QSTIB 04430 0.5 - 114 0 08527 0C70 0.4 30 2) 30 40 50 60 70 80 90 100 110 Cdre Flow (% Rata @

l I

4 I.

. . . . . - - . ., . - ~ - - - - - . - ._ - . - - . .- . - - - . . . - . . -

PECO Nuclear, Fuel & Servicco Divicion PECO-COLR-L2R4 l L2R4 Core Operating Limits Report Page 16, Rev. 2 TABLE 1 OPERATING LIMIT MINIMON CRITICAL PONER RATIO (OLMCPR)

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.

]

l l

TBV In Service TBV Out of RPT Out of and Service Service RPT In Service Opt. B Opt. A Opt. B Opt. A Opt. B Opt. A (Tau =0) (Tau =1) (Tau =0) (Tau =1) (Tau-0) (Tau =1)

BOC TO EOR - 1.30 1.33 1.37 1.40 1.37 1.42 2000 MNd/ST EOR -

2000 1.34 1.37 1.39 1.42 1.40 1.4R MNd/ST to EOC l

Notes:

1. When Tau does not equal 0 or 1, determine OLMCPR via linear interpolation.

PECO Nuclear, Fuel & Servicro Divicion PECO-COLR-L2R4 l'L2R4 Core Operating Limits Report Page 17, Rev. 2 FIGURE 10 POWER DEPENDENT MCPR LIMIT ADJUSTMENTS AND MULTIPLIERS THIS FIGURE IS VALID FOR THE RCF, ICF, MELLL, FWHOOS AND FWTR OPERATING DatDLINS I I

This Figure is Referred to by Technical Specification 3.2.3 l l

3.0

,3 2m , e0% no, omune uurT MCPR(P) = Kp

  • OPERARW UhET MCPR(100)

~~

K 1

{ FOR P<25% : NO THERMAL UMIT nOMTORim REQUIRED m D 2.6- .  :

L

~

FOR 25% a p = Pbypeas :(Pbypass = 30%)

2.39 2.4 ' ,

<= 60% Flow Kp = [ Kbyp + 0.C20(30% P)]IOLMCPR(1CD)

Kbyp = 124 R3R <= 80% CORE FLCW
g. 2.2'  :  : 124 = 285 FOR > 80% CORE FLIW L '

} l l FOR 30% <= P < 6 : Kp = 12 + 0.0134(45%. P) y 2.0 ' i  !

; R3R 45% == P < EDE
Kp = 1.15 + 0.00867(80% P) l I

1.8-  !, FOR 60% c= P : Kp = 1.00 + 0.003Mi(100%. P) f 1.6 - l l g  !  !

" 1.4 <  !  !

1J- .  !

l l 1.0 0 10 :D 30 40 50 (D 70 80 90 200 Pouse (% Rated)

I t

- - _. - . - . . = _. . -. .- .-

1 .

PECO Nuclear, Fuel & Cervicco Divicion PECO-COLR-L2R4 l L2R4 Core Operating Limits Report Page 18, Rev. 2 l

FIGURE 11 l

POWER DEPENDENT MCPR LIMIT ADJUSTMENTS AND MULTIPLIERS 4'

THIS FIGURE IS VALID FOR THE RPTOOS AND/OR TBVOOS OPERATING DOBOLINS This Figure is Referred to by Technical Specification 3.2.3 3.8 I l

1 35B OPERATifG UMT MCPR(P) = Mp

  • OPERATIPG UMT MCPR(100) l t ' I > m Roy

)

' FmPG%:POTHRM8LUMTh0NTORNGECURED 3.4 - j g. POUMTS SPEDFIED l  : b 'a:y

FOR2P4o P c Poppses:(Ptypass= 30%)

{ 3.0 -  ! i Vp=[% + 00E200%-PH/M100) l f  :

leyp = 25 FOR a 80%CCRE T'M 1

l 2'/D = 327 FOR> mCEREFLON

{2.6- j ' a80% Row FOR30%a P<6: Kp= 12 + QD134(49%-P) a  :  :

, ,g Fm 49%a P < m: Vp = 1.15 + Q3BS7(80%-P) 21 FOR80%a P: Fp = 1.00 + 0035(100%-l')

i  :  :

g  :  :

l M 1.8  ! i

}-  !

! 1.4 - l l l  :  :

i l
x 1.0 D 20 20 30 40 50 60 *10 80 90 100 Pomme (% Rated) l l

l l

4 i

_ . . _ _ . _ . _ . _ _ .m . _ _ _ _ . _ - . _ _ _ . . _ _ . . _ _ _ _ _ _ _ _ _ .- . . - . _ _ .

PECO Nuclear, Fuel & Ccrvicto Divi 0 ion PECO-COLR-L2R4 l L2R4 Core Operating Limits Report Page 19, Rev. 2 l FIGURE 12 l

FLON DEPENDIDIT MCPR LIMITS MCPR(F)

THIS FIGURE IS VALID FOR ALL OPERATING DCBEAINS This Figure is Referred to by Technical Specification 3.2.3 2.00 FORR(% RATED CORE FLCW, s a FORR(% RATED CORE FLOW) >= m MCPR(F) = [(M

  • M /100 + W)]* MCPR(F) s MAX (1.24,M
  • R/100 + Bf)

L90 ' D + 0.3132(40.W.)]

LED ' MAX FLOWNof Reach M 1 100.0 0.615 1.781 1140 0M 1.833 L'10 '

E M4Gh4M FLOWRATE = 1140%

E W uomunCwRuE= um 2.m . A Le-L30 '

I l

LE' )

L20 0 20 20 30 40 50 60 '10 80 90 200 220 Ocze Flcat (% Rate @

l l

l L

i

)

1 PECO Nuclear, Fuel & Services Divicion PECO-COLR-L2R4 l L2R4 Core Operating Limits Report Page 20, Rev. 2 >

TABLE 2 ROD BLOCK McKITOR SETPOINTS Neun4nal Trip Allowable Value r Setpoint LTSP 117.1% 118.3%

ITSP 112.3% 113.5% i 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.

l l

l i

. l

)

! )

I i

l l

1

i PECO Nuclear, Fuel f Scryices Divicion PECO-COLR-L2R4 l l L2R4 C0ro Operating Listits Report Page 21, Rev. 2 TABLE 3

' MAPLEGR SINGLE LOOP OPERATION (SLO) REDUCTION FACTOR l

i SLO reduction factor-u 1.r.0 for all Cycle 5 fuel types. l l

i I

i 1

I I

i l

P

i PECO Nuclear, Puel & Services Divicion PECO-COLR-L2R4 l L2R4 Cora Operating Limits Report Page 22, Rev. 2 TABLE 4 LINEAR BEAT GENERATION RATE LIMITS i

FUEL TYPE MAXIMUM VALUE GE6 13.4 kW/ft l l

, Gell 14.4 kW/ft ,

GE13 14.4 kW/ft l i

i 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). ,

l l

l.  :

?

l i

l I.

I I

2 r

I I

L

- . . _ . . . _ . . - - . - - . _ - . . - - . = - - - - . . . - - .-

l .

~

PECO Nuclear, Pu21 0 ServicO3 Divicion' PECO-COLR-L2R4 l L2R4 Core Operating Limits Report Page 23, Rev. 2 TABLE 5 TTGtBINE 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 l

Mav4== time af ter generation 0.30 sec i 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 t

Number of valves = 7 i

PECO Nuclear, Fu 1 E Scrvicao Divicion PECO-COLR-L2R4 4

l L2R4 Caro Optrating Limits Report Page 24, Rev. 2 i

i

\

l

TABLE 6

] Recirculation Pump Motor-Generator (MG) Set Scoop Tube Stops I i

i Recirculation MG Recirculation MG MAPFAC(F) Curve MCPR(F) Curve i

{ Mechanical Stop Electrical Stop Setpoint Maximum FLOW = Maximum FLOW =

Setpoint

(% Rated Core Flow) (figure 9, this COLR) (figure 12, this COLR) 2

(% Rated Core Flow) i 114 112 '114 114 ,

j I

1 i

i f

i l

1  !

TABLE 7 i

Control Rod Block Instrumentation 3 Reactor Coolant System Recirculation Flow Upscale Trips i

j i Nominal Trip Setpoint s 113.4%

j Allowable Value s 115.6% j l

l

,

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