ML20249B350

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Rev 1 to PECO-COLR-L2R4, COLR for LGS Unit 2 Reload 4,Cycle 5
ML20249B350
Person / Time
Site: Limerick Constellation icon.png
Issue date: 06/11/1998
From: Carmody J, Hoffman C, Mchale J
PECO ENERGY CO., (FORMERLY PHILADELPHIA ELECTRIC
To:
Shared Package
ML20249B348 List:
References
PECO-COLR-L2R4, PECO-COLR-L2R4-R01, PECO-COLR-L2R4-R1, NUDOCS 9806220347
Download: ML20249B350 (24)
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PECO Nuclear, Fuel & Services Division PECO-COLR-L2R4 l L'2R4 Core Operating Limits Report Page 1, Rev. 1 CORE OPERATING LIMITS REPORT FOR LIMERICK GENERATING STATION UNIT 2 l

RELOAD 4, CYCLE 5 Wb

//!i8 Prepared By:

c Date:

/

J. La. McHale Engineer Reviewed By:

dd Date:

NO

' C. Yd. Hof fnjiMn Ir. dependent Reviewer Approved By:

(2 Date:

0 Y

J. M. Carfibdy Manager Nuclear Design & Materials Branch 9006220347 990617 PDR ADOCK 050 33 P

~---r PECO Nuclo0r,-Fuci &-S0rvicO3 Divicien PECO-COLR-L2R4

-l L2R4 Coro Operating LimitG Ripart pig 3 2, R0v. 1 LIST OF EFFECTIVE PAGES Page(s)

Revision l'

1-24 1

l l

lT.

l l

l c

i e

L--:

PZCO NuclCar, Fuol & Strvicos Divicion PECO-COLR-L2R4

.l L2R4 Cora Operating Limit 3 Report Pcga 3, Rs.v. 1 INTRODUCTION AND

SUMMARY

Thi's 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 ARTS MAPLHGR thermal limit multipliers Rod Block Monitor (REM) data -

MAPLHGR single loop operation (SLO) reduction factor Linear Heat Generation Rate (LEGR)

Turbine Bypass Valve parameters Recirculation Pump Motor Generator (MG)

Set Scoop Tube 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.

This report is submitted in accordance with Technical Specification 6.9.1.9 of Reference 1.

Preparation of this report was performed in accordance with PECO Nuclear, Fuel & Services Division Procedure FM-300.

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

l i

e Maximum Extended Load Line Limit (MELLL) down to Bl% of l

rated' core flow during full power operation Increased Core Flow (ICF) up to 110% of rated core ficw

  • Feedwater Temperature Reduction (FWTR) up to 105 F during cycle extension operation

IGPLHGR 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).

I PECO NuclCar, FuOl & S;rvicO3 Division PECO-COLR-L2R4 l L2R4 Cora Operating Limito Report PIqa 4, rov. 1 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 cperation 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.

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

'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 penr-and flow-biased calculation.

l ROD BLOCK MONITOR SETPOINTS l

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

L

PECO Nuclear, Fuel & Services Division PECO-COLR-L2R4 l L2R4 Core Operating Limits Report Page 5, Rev. 1 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 S.

If these requirements cannot be met, the MCPR, MCPR(P) and MAPFAC ( P) limits for inoperable Steam Eypass System, known as Turbine Bypass Valve Out Of Service (TBVOOS), must be used.

i i

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

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 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 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 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.

PECO Nuclear, Fuel & Services Division PECO-COLR-L2R4 l L'2R4 Core Operating Limits Report Page 6, Rev. 1 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",

Cocket No. 50-353, License No. NPF-85.

l 2.

" Supplemental Relcad Licensing R~eport for Limerick Generating i

Station Unit 2 Reload 4 Cycle 5",

General Electric Company Document No. 24A5353, 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. 24A516SAA, Rev. O, January 1995.

5.

" Lattice-Dependent MAPLHGR Report for Limerick Genera'ing Station Unit 2 Relcad 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.

8. "DEC for Use of GE-11 Debris Resistant Lower Tie Plate", ECR No.

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 Recr ' red 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, Fuel & Services Division

'ECO-COLR-L2R4 l L2R4 Core Operating Limits Report Page 7, Rev. 1 Figure 1 MAXIMUM AVERAGE PLANAR LINEAR HEAT GENEF.ATION RATE (MAPLHGR)

VERSUS A.T. RAGE PLANAR EXPOSURE FUEL TYPE P9 CUB 331-9GZ (GE11-LGS 1 Reinsert)

~

This Figure is Referred to by Technical Specification 3.2.1 u..-

u..;

u...

5 l

3

n...

o 3

f....

n..

n..

n..

Average Plasar Exposure (GWd/ST)

Avg. Plan Avg. Plan Avg. Plan Exposure MAPLHGR Exposure MAPLHGR Exposure MAPLHGR (GWd/ST)

(kW/ft)

(GWd /S,T).

(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 1.0 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 Nuclear, Fuel & Services Division PECO-COLR-L2R4 l L2R4 Core Operating Limits Repo2ct Page 8, Rev. 1 Figure 2 l

l MAXIMUM AVERAGE PluuGR LINEAR HEAT GENERATION RATE (MAPLHGR)

VERSUS AVERAGE PLANAR EXPOSURE FUEL TYPE P9 CUB 354-12GL2 (Gell)

~

This Figure is Referred to by Technical Specifdeation 3.2.1 u..

u...

u...

_u..i f.

t

~

R

~

u...

g 5

I....

.f..

s...

Average Planar Exposure (GWd/ST)

Avg. Plan Avg. Plan Avg. Plan 2xposure MA2LHGR 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 53 11.70 17.5 11.79 55.0 7.00 6.0 11.84 20.0 11.49 57.9 6.60

PECO Nuc10 r, Fual & S;rvic'33 Divi 0 ion PECO-COLR-L2R4

. l L2R4 Cara Oper!. ting Limit 0 Rcport Pcg2 9, R;v. 1 Figure 3 MAXIMUM AVERAGE PLANAR LINEAR HEAT GENERATION RATE (MAPLHGR)

VERSUS AVERAGE PLANAR EXPOSURE l

FUEL TYPE P9 CUB 399-14GZ (Gell) l This Figure is Referred to by Technical Specification 3.2.1 l

l u,7 g

p

13...

.......[....

S f

nn...

2..

........s V

j 18 0 <

=. -. * *..'*. * * +

+ +*. ***-*

-**. * - * '. +++ - -**--.

I

.........l.........!.................:.......:........

6.e e.e as.e as.e so.o es.e so.s se.o Average Planar Exposure (GW4/ST)

Avg. Plan Avg. Plan Avg. Plan Exposure MAPLHGR Exposure MAPLHGR Exposure MAPLHGR (GWd/ST)

(kW/ft)

(GWd/ST)

(kW/ft)

(GWd/ST)

,{.tW/ f t )

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 25.0 9.53 2.0 10.95 10.0 12.09 40.0 8.91 3.0 11.1U 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

t l

l 1

PECO Nuclear, Fual & S;rvicOO Divicien PZCO-COLR-L2R4 i

l L2R4 Cora Operacing Limito Report Pcg3 10, Rev. 1 l

Figure 4 MAXIMUM AVERAGE PLANAR LINEAR HEAT GENERATION RATE (MAPLHGR)

VERSUS AVERAGE PLANAR EZ.POSURE FUEL TYPE P8CIB219-4GZ (GE6)

This Fig.are is Referred to by Technical Specification 3.2.1 is.,I

,,. e.

{

1 y

g g

g

......................................... K..

1,...

5 a

.g

,,. e.

4 e

gp g.

.g i

i as.e s.e s.e to.e is.s so.e as.e so.e Average Planar Exposure ( GW4/ST) 1 Avg. Plan Avg. Plan Avg. Plan i

Exposure NAPLHGR Exposure MAPLHGR Exposure MAPLHGR (GWd/ST)

(kW/ft?

(GWd/ST)

(kW/ft),

(GWd/ST)

(kW/ft) 0.2 11.90 10.0 11.90 25.0 11.60 1.0 11.90 15.0 11.90 30.0 11.20 5.0 12.00 20.0 11.80

PZCO NuclCcr, Fu31 & S rvic;3 Divicion PECO-COLR-L2R4 l L2R4 Cora Oper0. ting Limit 0 R p3rt Pcg3 11, R v.

1 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.e...~

13.e U

p x

11.s oc h.

l 11.s so.s 9

e so.s e.o s.e me.e is.e so.e as.e me.e Aveerage Planar F.xposure (GWd/ST) i I

l

. Avg. Plan Avg. Plan Avg. Plan l

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

1.0 11.90 15.0 12.00 30.0 10.80 5.0 12.00 20.0 11.90 t

=PECO NuclCOr, Fu3l is S rvitC3 Divicion PECO-COLR-L2R4 l L2R4 Cora Operating Limito Report Pag 3 12, rov. 1 j,

i Figure 6 MAXIMUM AVERAGE PLANAR LINEAR HEAT GENERATION RATE (MAPLHGR)

VERSUS AVERAGE PLANAR EXPOSURE FUEL TYPE P9CTB416-15GZ (GE13)

~

This Figure is Referred to by Technice.1 Specification 3.2.1 1'

1 u...

4......:......

u...

s

_u...

.y...

d a

g 5'

3............

n...

Average Planar Exposure (GWd/ST)

Avg. Plan Avg. Plan Avg. Plan Exposure MAPLHGR Exposure MAPLHGR 2xposure MAPLHGR (GWd/ST)

(kW/ft)

(GWd/ST)

(kW/ft)

(GWd/ST)

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

I PECO-NuclOOr, Fuci & S0rvic0c Divicion PECO-COLR-L2R4 l L2R4 Coro Operating Limita RIport PIga 13, rov. 1 FIGURE 7 l

POWER DEPENDENT MAPLHGR MULTIPLIER MAPFAC(P)

)

l THIS FIGURE IS VALID FOR THE RCF, ICF, HELLL, FWHOOS AND FWTR OPERATING DOMAINS This Figure is Referred to by Technical Specification 3.2.1 l

..e..._.._

e.e.

E g e e<

d o.

I e.1 0.63 h

< 60% Flow MAPLHGR(P) = MAPFAC(P)

\\ :; O.55 MAPLHGRstd = Standard MAPLHGR Lrnns g'*

O.48 Ft;f 25% > P : No Thermal Limits hennaring Reawed g

No Limits Specited E

e.4 -

l l

For 25% c. P < 30% ; MAPFAC(P). 0.55 + 0.004(P 30%)

g

> 60% F'ow For <= 60% Core Flow g

g e,3 <

{

MAPFAC(P). 0.50 + 0.004(P 30%)

For > 60% Core Flow b

e..

For 30% c. P -

MAPF ev(P) =1.0+ 0.005224(P.100%)

l l

e.t <

l l

e.e e

as se se se se se to as se ase Power (4 Rated) l l

l l

1 I

i l

PECO Nuclear, FuOl & SCrvicO3 Division PECO-COLR-L2R4

-l L2R4 Cora Operr. ting Limit 0 RCport PCga 14, Ecy. 1 l

FIGURE 8 POWER DEPENDENT MAPLHGR HULTIPLIER MAPFAC(P)

THIS FIGCRE IS VALID FOR THE RPTOOS AND/OR TBVOOS OPERATING DOMAINS This Figure is Referred to by Technical Specification 3.2.1 I

1 s.e, -

9.D.

l E

y e...

I I e.,.

i s.s'

<= 60% Few 0.55 N,

MAPLHOR(P) = MAPF AC(P)

as 4

053

,0,, s s.

MAPLHGRat1 = Standard MAPLHGR Umus l3 0.48

}

For 25% > P : No Thermal Limits Marutorrig Requred s.4 -

0.40 No Umas Spoofied y

0.35 For 25% <= P c 30% : MArkAC(P) = 0.53 + 0.01(P. 30%)

3,,,,

{

(;

> 60% Flow For <= 60% Care Flow j

l MAPFAC(P) = 0.40 + 0.01(P 30%)

For > 60% Core Flow

,s.t.

=

For 30% <= P :

MAPFAC(P) = 0.84+ 0.004143(P 100%)

f l

0.1 <

l l

l l

s.e 10 33 30 48 54 50 70 et 99 100 Power (% Rated)

PECO'NuclOOr, YuOl & S;rvicOa Divicion PECO-COLR-L2R4 I

l L2R4 Coro OperOting Limito Report Pega 15, R v.

1 FIGURE 9 1

FLOW DEPENDENT MAPLHGR MULTIPLIER MAPFAC(F)

THIS FIGURE IS VALID FOR ALL OPERATING DOMAINS

~

This Figure is Referred to by Technical Specification 3.2.1 l

1.1 1.e.

C

.e.

e I

MAX, FLOW = 100%

o MAX. FLOW = 114%

f MAPLNGR(F)- MAPFACl

MAPLHGRstd. STANDARD MAPLHGR LIMTS b

MAPFACf(F). MNIMJM (1.0, Af ' We /100 + Bf) 5-

5. ' ' 8 '

We % RATED CORE FLOW e

AND Af, Of ARE CONSTANTS GIVEN BELOW:

I MAX. COAE FLOW f% RATED)

Af Rf 109.0 0.0778 0.4430 e.s.

114.0 04827 0.4070 e.4 to se se as se se vs as es ses sie Core Flow (% Rated) k

PZCO Nuc100r, Fuol &'S2rvic00 Divicion PECO-COLR-L2R4 l L2R4 Cora OpOrating Limito Rrport Pcg3 16, Rov. 1 TABLE 1 OPERATING LIMIT MINIMUM CRITICAL POWER RATIO (OLMCPR)

Use in conjunction with Figures 10, 11 and 12.

This table is valid for two-loop operation.

e Add 0.01 to the OLMCPR when in Single Loop Operation.

  • This tabit, is valid for all Cycle 5 fuel types.

This table is referred to by Technical Specification 3.2.3.

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)

(Taus0)

(Tau =1)

(Tau =0)

(Tau =1) t BOC TO EOR -

1.30 1.33 1.37 1.40 1.37 1.42 2000 mwd /ST EOR -

2000 1.34 1.37 1.39 1.42 1.40 1.48 mwd /ST to EOC i

Notes:

l

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

PECO Nuclecr, FuO1 & S:rvicO3 Divicion PECO-COLR-L2R4 l L2R4 Coro OperOting Limito Rtport Paga 17, R2v. 1 FIGURE 10 POWER DEPENDENT MCPR LIMIT ADJUSTMENTS AND MULTIPLIERS

'THIS FIGURE IS VALID FOR THE RCF, ICF, MELLL, FWHOOS AND FWTR OPERATING DOMAINS This Figure is Referred to by Technical Specification 3.2.3 s.e

~

~

2E0 k

W > 60% Flow OPERATING LIMIT MCPR(P) = Kp

  • OPERATING LIMT MCPR(100)

W FOR P<25% : NO THERMAL UMIT MONITORING REQUIRED 2.65 NO LIMTS SPECIFIED l

l FOR 25% <= P < Pbypass :(Ftypass = 30%)

0 2.39 I a.4 '

<= 60% Flow Kp = [ Kbyp + 0,030(30%- P)} / OLMCPR(100)

Kbyp = 2.24 FOR <= 60% CORE FLOW 8' a.:.

{

2.24

= 225 FOR > 60% CORE FLOW

. ti FOR 30% <= P < 45% : Kp = 1.28 + 0.0134(45%. P) u 3,e,

FOR 45% <= P < 60% : Kp = 1.15 + 0.00867(60%. P)

FOR 60% <= P :

Kp = 1.00 + 0.00375(100%. P) 1.s -

I A* s.a.

l I

N e

3

,s.

3 a

2...

a to ao as as se so to se se see Power (4 Rated) l l

PECO NuclOOr, Fuci & S;rvic33 Division PECO-COL % L.R4 l L2R4 Cora OptrOting Limito R port P2g3 18, Roy. 1 FIGURE 11 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 i.e 3.58 OPERATING LIMT MCPR(P). Kp

  • OPERATING LMT MCPR(100) g
g > 60% Flow FOR P<25%
NO THERMAL LMT MONITORING REQUIRED

{

NO LMTS SPECIFIED 3.27 j

FOR 25% i. P < Pbypass :(Pbypass = 30%)

o f

Kp = ( Kbyp + 0.062(30% - P)) / OLMCPR(100)

.e.

h Kbyp = 2.39 FOR <= 60% CORE FLOW 8,

2.70

= 3.27 FOR > 60% CORE FLOW 8

c. 60% Flow FOR 30% <. P < 45% : Kp = 1.28 + 0.0134(45%. P)

FOR 45% < P < 60% : Kp - 1.15 + 0.00867(60% - P) 2M

{,f,,

l l

FOR 60% c. P :

Kp = 1.00 + 0.00375(100% P) 1.s, N

W m 1.s.

I

=

e a

a.e e

se as se so so se to se se see Power (% Rated) l 1

PECO NuclOcr, FuOl & S3rvic33 DiviDion PECO-COLR-L2R4 l 42R4 Cora Operating Limito R1 port Ptg3 19, Rsv. 1 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 3.se FOR We(% RATED CORE FLOW) < 40%

FOR We (% RATED CORE FLOW) >- 40%

MCPR(F) = [(At

  • We /100 + Bf))
  • MCPR(F). MAX (124, Al
  • We /100 + Bf)

[1 + 0.0032(40- Wc)]

1.se -

MAX FLOW (% of Rated)

Af Bf 109.0

-0.615 1.781 114.0

-0.632 1E33 1.f e.

3 E

MAXIMUM FLOW RATE = 114.0%

E.

p M g.se.

MAXIMUM FLOW RATE = 109.0%

)

1.s e.

1.3e.

12e -

1.t o e

to se se se se se to se se son sto Core Flov (% Rated) l l

j *.

PECO Nuclear, Fual & S rvicO3 Divicion PECO-COLR-L2R4 l

l L2R4 Coro OperOting Limits Report PcgO 20, R0v. 1 i

TABLE 2 ROD BLOCK MONITOR SETPOINTS Nominal Trip Allowable Value Setpoint l

l LTSP 117.1%~

118.3%

ITSP 112.3%

113.5%

HTSP 107.3%

108.5%

DTSP 92%

89%

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These setpoints are based on a MCPR limit of 1.30 and are consistent with a REM filter time constant between.0.1 seconds and 0.55 seconds.

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

~ PECO NuclcOr,'FuO1 & S0rvicG3 Division PECO-COLR-L2R4 o

l L2R4 Cora Opercting Limits R; port Ptga 21, RIv. 1 TABLE 3

{

MAPLHGR SINGLE LOOP OPERATION (SLO) REDUCTION FACTOR

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-SLO reduction. factor = 1.00 for all Cycle 5 fuel types.

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PECO Nuclocr,.Fu21 & SIrvicO3 Divicion PECO-COLR-L2R4 l L2R4 Cara Operating Limito Report Pcg3-22, R;v. 1 TABLE 4 LINEAR HEAT GENERATION RATE LIMITS FUEL TYPE MAXTMUM 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).

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.PECO NuclOcr, Fu 1 & S0rvicO3 Divicien PECO-COLR-L2R4 l L2R4 Cora Operating Limito Rcport Pag 3 23, RLv. 1 TABLE 5 TURBINE BYPASS VALVE PARAMETERS TURBINE BYPASS SYSTEM RESPONSE TIME

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Maximum delay time before start 0.10 sec of bypass valve opening following generation of the turbine bypass valve flow signal Msximum 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 OP'ERABILITY I

j Number of valves = 7 1

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PECO Nuclear, Fuel & Services Division PECO-COLR-L2R4 l L2R4 Core Operating Limits Report Page 24, Rev. 1 TABLE 6 Recirculation Pump Motor-Generator (MG) Set Scoop Tube Stops Mechanical 5 109%

Electrical 5 107%

TABLE 7 Control Rod Block Instrumentation Reactor Coolant System Recirculation Flow Upscale Trip Nominal Trip Setpoint 5 113.4%

Allowable Value 5 115.6%

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