Text

Rev 1 to COLR for LGS Unit 1,Reload 7,Cycle 8
	ML20198C715
Person / Time
Site:	Limerick
Issue date:	12/10/1998
From:	Carmody J, La Mchale J, Payton S; PECO ENERGY CO., (FORMERLY PHILADELPHIA ELECTRIC
To:	;
Shared Package
ML20198C708	List: ML20198C702; ML20198C715;
References
	PECO-COLR-L1R7, PECO-COLR-L1R7-R01, PECO-COLR-L1R7-R1, NUDOCS 9812220145
	Download: ML20198C715 (26)
	v • d • e

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.PZCO Nuclccr FuOl & SOrvicOO Divicion PECO-COLR-L1R7 L1R7 Cara OpOrcting Limita R port Pag 3 1, rov. 1 CORE OPERATING LIMITS REPORT FOR LIMERICK GENERATING STATION UNIT 1 RELOAD 7, CYCLE 8 Prepared By: A,h))Eh4dQ Date: 12 JO 98 I) . I '

John La. McHale Engineer Reviewed By: , % Date: /2[/v /98

.I Stephen F. Payton Independent Reviewer Approved B3 guw Date: /2[/o [

y -

u James M. Carmody Manager Nuclear Design & Materials Branch 9812220145 981215 PDR ADOCK 05000352 P PDR ; _

PCCO NuclOOr Fuoi is-SOrvicO3 Divicion

PECO-COLR-L1R7 L1R7 Coro OpOrOting Limita R port Paga 2, R3v. 1 I

LIST OF EFFECTIVE PAGES

! Page(s) Revision l 1 - 26 1 l

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', PCCO Nuc100r Fuci & S;rvicOO Divicicn PECO-COLR-L1R7 L1R7 Caro OpOrOting Limita R pert Pcg3 3, R0v. 1 l'

INTRODUCTION AND

SUMMARY

l This report provides the following cycle-specific parameter limits for Limerick 3enerating St6 tion Unit 1 Cycle 8 (post failed fuel outcoe, 1M32)

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) data '

- 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

Reacter 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 7 :ordance with Technical Specification

6. 9.1.9 of Reference 1. Pr aparation of this report was performed ;

in accordance 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:

- Maximum Extended Load Line Limit (MELLL) .down to 81% of rated core flow during full power operation

:ncreas'ed Core Flow (ICF) up to 110% of rated core flow

Feedwa:er Temperature Reduction (FWTR) up to 105 F during cycle extension operation

'e Feedwater Heater Out of Service (FWHOOS) up to 60 F

'feedwater temperature reduction at any time during the cycle prior to cycle extension.

Further infor ation on the cycle specific analyses for Limerick 1 Cycle 5 and : heir associated cperating domains is available in l References 2, 15, 17 and 19. Additional information on the inputs used in perf rming the Limerick 1 Cycle 8 specific analyses are available in References 3 and 4.

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l PECO Nuc103r Fr.cl & S0rvicGO Divicion PECO-G LR-L1R7 L1R7 Coro Op3rcting Limitc Rcport P ga 4, Rov. 1 l

MAPLHGR LIMITS l 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 8. These figures are used when hand calculations are required as specified j in Technical Specification 3.2.1. The MAPLHGR limit curves of Figures 1 through 8 were generated from References 5.through 8. 1 No reduction in MAPLHGR limits is required under ARTS during )

single loop operation (Table 3). The use of the single loop reduction factor, specified in Table 3, is documented in Reference ,

2. l 1

MCPR LIMITS The MCPR value for use in Technical Specification 3.2.3 is given in Table 1. This table is derived from the Reference 2 analysis and is valid for all Cycle 8 fuel types and operating i 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 (RP'IDOS ) and/or inoperable Steam Bypass System (TBVOOS). These two options represent the Equipment Out of j Service (EOOS) condition. I 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 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, including SLO. However, there are two sets of power-dependent "J.PLHGR 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.

The power dependent MAPLHGR multipliers and power dependent MCPR

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adjustments / multipliers are sufficiently generic to permit both two i recirculation loop operation and SLO in the operating domains specified.

The apprcpriate value of the flow-dependent parameters is chosen based on the maximum allowable core flow setting (for the mechanical stop) presented in Table 6.

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.P BCO NuclOcr Fuol & SOrvic0c Divicion PECO-COLR-L1R7 L1R7 Cora Optrating Limits R port Pags 5, RCv. 1 The ARTS adjustments and multipliers are shown in Figures 9 through 14. Thermal limit monitoring must be performed with the more limiting .MCPR and MAPLHGR limits resulting from the power- and flow-biased calculation. The use of ARTS multipliers shown in Figures 9 through 14 is documented in References 9 through 11, 16

.and 18.

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. These values are for use with Technical Specification 3.3.6. The use of the setpoints specified in Table 2 is documented in References 2, 9, 12, and 13.

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 5. (GE proprietary).

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) and MAPFAC (P) limits for inoperable Steam Bypass System, known as Turbine Bypass Valve Out Of Service (TBVOOS), must be used. The turbine bypass valve parameters of Table 5 are documented in References 3 and 4.

' RECIRCULATION PUMP TRIP OPERABILITY If the recircula: ion pump trip is inoperable, then the MCPR, MCPR(P) and MAPFAC (P) limits for Recirculation Pump Trip Out Of Service ( RP'IDOS ) , mus: be used. Further information about the RPTOOS. condition is atailable in References 9 and 11.

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 se scoop tube mechanical and electrical stop shall be demonstrated PERABLE, with overspeed setpoints less than or equal to specifie:i values, at least once per 24 months. The

PECO Nucloor Fuol & SOrvic0c Divicion PECO-COLR-L1R7 L1R7 Coro OpGrating Limito RCport Pigo 6, R0v. 1 settings of these stops may be changed during the cycle. in a,ccordance with changes in operational strategy. These values are cycle-specific and can be found in Table 6 of this COLR. Further infor.ation as to how the MG set limiting setpoints relate to other parameters in the Technical Specifications and COLR may be obtained from References 9 through 11.

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. Further details on these setpoints may be obtained from Reference 14.

REFERENCES

1. " Technical Specifications and Bases for Limerick Generating Station Unit 1", Docket No. 50-352, License No. NPF-39.

2. ." Supplemental Reload Licensing Report for Limerick Generating S:ation Unit 1 Reload 7 Cycle 8", General Electric Company 2 cument No. J11-03191SRLR, Rev. O, March 1998.

3. Le:ter, R. M. Butrovich to J. M. Carmody, " Limerick 1 Cycle 8 Resolved OPL-3 Revision 1", December 2, 1997.

4. Letter, R. M. Butrovich to J. M. Carmody, " Limerick 1 Cycle 8

esolved OPL-3 and Revised FRED Form", November 21, 1997.

5. " Lattice Dependent MAPLHGR Report for Limerick Generating Station Unit 1 Reload 7 Cycle 8", General Electric Company 2:cument No. J11-03191 MAPL, Rev. O, March 1998 (GE proprietary).

6. " Lattice Dependent MAPLHGR Report for Limerick Generating 5:ation Unit 1 Reload 6 Cycle 7", General Electric Company

ument No. 24A5185AA, Rev. O, January 1996 (GE prcprietary).

7 " Lattice Dependent MAPLHGR Report for Limerick Generating 5:ation Unit 1 Reload 5 Cycle 6", General Electric Company

':::ument No. 23A7232AA, Rev. 1, July 1995 (GE proprietary).

l PCCO Nuc1 Car Fus1 & Scrvicco Divicion

. PECO-COLR-L1R7 L1R7 Carc Op3rcting LimitG R p3rt Pcg3 7, R3v. 1 l~

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., 8..- " Lattice.< Dependent MAPLHGR : Report for Limerick Generating Station Unit 2 Reload 2 _ Cycle 3", General Electric Company Document No. 23A7200AA, Rev. 3, July 1994 (GE proprietary),

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!- 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. Letter, G. V. Kumar to K. M. McGinnis, " Limerick ARTS Application with Equipment Out-of-Service (EOOS)", Dec. 10, l .1993.

11. Letter,_R. M; Butrovich to'J. M. Carmody, " Revised Limerick 1 Cycle.8 ARTS Thermal Limits Curves", March 12, 1998.. j

- 12. " Power Rerate Condition' Setpoint Calculations for the Philadelphia- Electric Company Limerick' Generating Station Units 1 & 2", GE Document.-No. GE-NE-209-20-0993-2, August. I 1994. l

.13 . "GE NSSS Setpoints Required to Support Power Rerate", PECON i Calculation No. LE-0082, July 27,1995.

14. " Safety Review for Limerick Generating Station Units 1 and 2, 110% Increased Core Flow Operation and Final Feedwater Temperature Reduction", GE Nuclear Energy Document 'NEDC--

~ 32224P, Rev. 1, October 1994.

15.. . Letter, R. M. Butrovich to K. W. Hunt, " Limerick 1 - Cycle 7 Exposure", April 6, 1998. -l

16. Letter,-R. M. Butrovich to K. W. Hunt,."MCPR(P) Curves for SLO during Limerick 1 Cycle 8", April 10, 1998.

- 17. Letter, R. M. Butrovich to K. W. Hunt, " Limerick 1 Cycle 8 Core Loading Change", April 30, :998.

18. Letter, J. L'. Casillas to G. C. Storey, " Applicability of Flow

-MCPR. Limit to Single Loop' Operation", May 5, 1998.

- 19. Letter, R. M. Butrovich_to K. W. Hunt, " Safety Review of the:

Limerick 1 Cycle 8 Supplemental Reload Licensing Report due to Licensing Bases Changes", Dece:rber 10, 1998.

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PECO Nuclocr Fuoi & S;rvicOO Divicion PECO-COLR-L1R7 L1R7 Coro Op0rcting Limito Rcport P2gE 8, RGv. 1 i

FIGURE 1 i

MAXIMUM AVERAGE PLANAR LINEAR HEAT GENERATION RATE (MAPLHGR) VERSUS l AVERAGE PLANAR EXPOSURE FUEL TYPE P9CTB404-14GZ (GE13) l THIS FIGURE IS REFERRED TO BY TECHNICAL SPECIFICATION- 3.2.1 13.0 l j

I 12.0 11.0

( \

g 10.0 A h 0.0

.'0 N\ '

N 20

\x

.0 0.0 5.0 10.0 15.0 20.0 25.0 30.0 35.0 40.0 45.0 50.0 55.0 60.0 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 10.53 10.0 12.12 40.0 8.96 1.0 10.74 12.5 12.13 45.0 8.31 2.0 10.93 15.0 11.99 50.0 7.64 3.0 11.14 17.5 11.74 55.0 6.94 4.0 11.30 20.0 11.43 57.35 6.60 5.0 11.44 25.0 10.81 6.0 11.59 30.0 10.19 l 8.0 11.90 35.0 9.58

PZCO Nuc1COr FuOl & SOrvicO3 Divicicn PECO-COLR-L1R7 L1R7 Ccro Op; rating Limit 0 RCp3rt Paga 9, rov. 1 FIGURE 2 MAXIMUM AVERAGE PLANAR LINEAR HEAT GENERATION RATE (MAPLHGR) VERSUS AVERAGE PLANAR EXPOSURE FUEL TYPE P9 CUB 384-12GZ (Gell) l THIS FIGURE IS REFERRED TO BY TECHNICAL SPECIFICATION 3.2.1 l 13.0 l

12.0 l N '

11.0 # '

/ N 10.0 i

9.0 N

m N s.O '

70 xs 6.0 0.0 5.0 10.0 15.0 20.0 25.0 30.0 35.0 40.0 45.0 50.0 55.0 60.0 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 10.46 17.5 11.41 55.0 6.72 2.0 10.75 20.0 11.10 56.1 6.56 4.0 11.03 25.0 10.50 6.0 11.33 30.0 9.91 8.0 - 11.63 35.0 9.31 10.0 11.91 40.0 8.71 12.5 11.90 45.0 8.08 15.0 11.71 50.0 7.41

'PECO NuclGOr Fuol & S rvic2O Division PECO-COLR-L1R7 L1R7 Coro Op0rcting Linita R psrt PIga 10, rov. 1 i

, FIGURE 3 MAXIMUM AVERAGE PLANAR LINEAR HEAT GENERATION RATE (MAPLHGR) VERSUS AVERAGE PLANAR EXPOSURE FUEL TYPE P9 CUB 331-9G5.0 (GE11-LGS 1 Reinsert)

THIS FIGURE IS REFERRED TO BY TECHNICAL SPECIFICATION 3.2.1 13.0 12.0 f %

11.0 <

~ 10.0 i N I.0 x i x

.0 \

7.0

\ Y 8.0 00 5.0 10.0 15.0 20.0 28.0 30.0 35.0 40.0 45.0 50.0 66.0 60.0 Average Planar Exposure (Gwd/ST)

Avg Plan Avg Plan Avg Plan Exposure MAPLHGR Exposure MAPLHGR Exposure MAPLHGR l (GWd/ST) (kw/ft) , GWd/ST)

( (kw/ft) (GWd/ST) (kw/ft) 0.0 11.76 12.5 12.67 35.0 9.95 2.0 12.01 15.0 12.39 40.0 '9.30 4.0 12.16 17.5 12.08 45.0 8.62 6.0 12.32 20.0 11.77. 50.0 7.90 8.0 12.49 25.0 11.17 55.0 7.16 10.0 12.67 30.0 10.57 58.7 6.52

. . . . . _ . _ _ . _. _ . . . _ . ._____m____ _ ._ _.-.--_ __. _ . _ _ -

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' ' PECO Nuclear Fuol & SOrvicoc Division PECO-COLR-L1R7 L1R7 Cero Op;rcting Limito Rspart Pcga 11, ROV. 1 FIGURE 4 1

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l MAXIMUM AVERAGE PLANAR LINEAR HEAT GENERATION RATE'(MAPLHGR) VERSUS AVERAGE. PLANAR EXPOSURE FUEL TYPES: P8CIB219-4GZ-100M and P8CIB219-4GZ-80M (GE6)

THIS FIGURE IS REFERRED TO BY TECHNICAL SPECIFICATION 3.2.1 1 13.0 l

12.0 11.0 g 10.0 5 1 s- ,

e.0 5.0

'e'.0 6.0 0.0 5.0 10.0 15.0 20.0 25.0 30.0 35.0 AVERAGE PLANAR EXPOSURE (GWdST)

Avg Plan Avg Plan Avg Plan Exposure MAPLHGR Exposure MAPLHGR Exposure MAPLHGR (GWd/ST) (kwlft) ' (GWd/ST) (kw/ft) (GWd/ST) (kwift)

' O.0 11.90 5.0 12.00 20.0 11.80

. 0.2 11.90 10.0 11.90 25.0 11.60 1.0 11.90 15.0 11.90 30.0 11.20 o

-W

__ . . . . _. > _ _ _ ..___.. . - ..___._. _ ._.-. - . _ _ . . ~ _ . . _ _ _ . _ _ _ . . . _ . _ . _ . . _ _

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PECO Nuc1Cor Fuol & S0rvicac Divicion l * *

' PECO-COLR-L1R7 i

{ L1R7 Coro Op3rcting Limito R port Pcg3 12, Rsv. 1 i

FIGURE 5

MAXIMUM AVERAGE PLANAR LINEAR HEAT GENERATION RATE (MAPLHGR) VERSUS AVERAGE PLANAR EXPOSURE '

I FUEL TYPE PSCIB176-4GZ-80M (GE6) !

THIS FIGURE IS REFERRED TO BY TECHNICAL SPECIFICATION 3.2.1 l i'

I 13.0 I

l 12.0 r -

1 I

11.0 fr I y 10.0 g 1 8

3

% ~ s.0 m

l 8.0 7.0 6.0 0.0 5.0 10.0 15.0 20.0 25.0 30.0 35.0 AVERAGE PLANAR EXPOSURE (GWd'Sh Avg Plan Avg Plan Avg Plan Exposure MAPLHGR Exposure MAPLHGR Exposure MAPLHGR

- (GWd/STL (kw/ft) (GWd/ST) (kw/ft) (GWd/ST) (kw/ft) 0.0 11.80 5.0 12.00 20.0 11.90 0.2 11.80 10.0 12.00 25.0 11.70 1.0 11.90 15.0 12.00 30.0 10.80 i.

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PECO Nuc10er'FuO1 & S rvic03 Divicicn PECO-COLR-L1R7 i L1R7 C3ro Op;rOting Limito R port P ga 13, rov. 1 i

FIGURE 6 MAXIMUM AVERAGE PLANAR LINEAR HEAT GENERATION RATE (MAPLHGR) VERSUS AVERAGE PLANAR EXPOSURE 1 FUEL TYPE P9CTB412-13GZ (GE13) l THIS FIGURE IS REFERRED TO BY TECHNICAL SPECIFICATION 3.2.1 13.0 1

j 12.0

'\

[

11.0 r ,

I 10 .0 L N 1 5

'N 9.0 a.0 7.0

'\ -

6.0 0.0 5.0 10.0 15.0 20.0 25.0 30.0 35.0 40.0 45.0 50.0 55.0 60.0 AVERAGE PLAN AR EXPOSURE (GWd/ST)

Avg Plan Avg Plan Avg Plan Exposure MAPLHGR Exposure MAPLHGR Exposure MAPLHGR (GWd!ST) (kwlft) (GWd/ST) (kw!ft) (GWd/ST) (kw/ft) 0.0 10.89 7.0 11.92 25.0 10.95 0.2 10.95 8.0 12.02 30.0 10.33 1.0 11.04 9.0 12.12 35.0 9.71 2.0 11.18 10.0 12.21 40.0 9.08 3.0 11.33 12.5 12.20 45.0 8.44 4.0 11.49 15.0 12.08 50.0 7.76 5.0 11.65 17.5 11.88 55.0 7.06 6.0 11.78 20.0 11.53 57.9 6.63

PZCO Nuclcar Fuol & SOrvic00 Divicien PECO-COLR-L1R7 L1R7 C0ro OpOrcting Limito R^ port Preg 3 14, RSv. 1

. FIGURE 7 MAXIMUM AVERAGE PLANAR LINEAR HEAT GENERATION RATE (MAPLHGR) VERSUS AVERAGE PLANAR EXPOSURE FUEL TYPE P9CTB413-14GZ (GE13)

THIS FIGURE IS REFERRED TO BY TECHNICAL SPECIFICATION 3.2.1 i

13.0 12 0

[ '\

11.0 f '

F 10 .0 \

l N h 9 .0 ( ' l s.0 N,

1.0

.0 0.0 ~ 5.0 10.0 15.0 20.0 25.0 30.0 35.0 40.0 45.0 $0.0 55.0 60.0 AVERAGE PLANAR EXPOSURE (GWd/ST)

- Avg Plan Avg Plan Avg Plan I Exposure MAPLHGR Exposure MAPLHGR Exposure MAPLHGR (GWd'ST) (kwlft) (GWd/ST) (kwlft) (GWd/ST) (kwlft) 0.0 10.76 7.0 11.90 25.0 10.95 0.2 10.83 8.0 - 12.01 30.0 10.33 j 1.0 10.97 9.0 12.11 35.0 9.71 1 20 11.18 10.0 12.21 40.0 9.08 3.0 11.34 12.5 12.19 45.0 8.44 4.0 11.50 15.0 12.07 50.0 7.76 5.0 11.66 17.5 11.87 55.0 7.06 6.0 11.78 20.0 11.58 57.9 6.63

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

PECO Nuc100r Fusi & S rvicOc Divicion

PECO-COLR-L1R7 L1R7 C ra Op rcting Limito R;p3rt Pcg3 15, R2v. 1 l

r FIGURE 8 i

i .

1 MAXIMUM AVERAGE PLANAR LINEAR HEAT l GENERATION RATE (MAPLHGR) VERSUS '

l AVERAGE PLANAR EXPOSURE FUEL TYPE P9 CUB 354-12GZ2 (GE11-LGS 2 Reinsert) l THIS FIGURE IS REFERRED TO BY TECHNICAL SPECIFICATION 3.2.1 13.0 12.0 /% ' I 11.0 3 F 10.0 N

0.0 0.0 x

7.0 x

00 0.0 5.0 10.0 15.0 20.0 25.0 30.0 35.0 40.0 45.0 50.0 65.0 60.0 Average Planer Exposure (GWd.ST)

Avg Plan Avg Plan Avg Plan Exposure MAPUDR Exposure MhPIKIR Exposure HAPIJCR (OHd/sT) (kw/C:) (ani/n) (kw/ft) (cus/m) (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 57.85 6.60 l

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PECO Nuc10Cr Fuol & S rvicO3 DiviDicn PECO-COLR-L1R7 L1R7 Caro Op;rcting Linito R port Pcgo 16, R0v. 1

, FIGURE 9 POWER DEPENDENT MAPLHGR MULTIPLIER MAPFAC(P)

THIS FIGURE IS VALID FOR THE RCF, ICF, MELLL, FWHOOS AND FWTR OPERATING DOMAINS THIS FIGURE IS REFERRED TO BY TECHNICAL SPECIFICATION 3.2.1 s.: . _

t.0-

{

E /

d 0.0 -

o b

2 m 0.63 E .

MAPLHGR(P) MAPFAC(P)

MAPLHGRstd s 60% Flow \

g 0.0 - 4 {

0.53 g 0.55 WMsW - SWd MAMGR Umh 0.50 0.48 , For 25% > P : No Thermal Umits Monstoring Required No Umits Specified

0. 4 - ! l 8 > 60% Flow j j For 25% s P < 30% : MAPFAC(P) . 0.55 + 0.004(P - 30%)

,- ; ; For s 60% Core Flow MAPFAC(P) = 0.50 + 0.004(P 30%)

,,,. j j For > 60% Core Flow

! l For 30%s P : MAPFAC(P) = 1.0+ 0.005224(P .100%)

l l l l l l 0.0 0 to 20 30 40 50 EO 70 00 00 100 g Power (% Rated)

+ . ,

PCCO Nuc100r Fuol & SOrvic00 Div10 ion PECO-COLR-L1R7 L1R7 Ccra Op;rcting Limito R; port Pags 17, RGv. 1 FIGURE 10 POWER DEPENDENT MAPLHGR MULTIPLIER MAPFAC(P)

THIS FIGURE IS VALID FOR RPTOOS AND/OR TBVOOS OPERATING DOMAINS THIS FIGURE IS REFERRED TO BY TECHNICAL SPECIFICATION 3.2.1 1.2 1.e<

E h

it<

2 0.84.....................................................................................................

of , , , ,

S.

W u

5 5e .s - 3 soy,gjow g' q MAPUQP) . MAPF AC(P)* MAPLNGRsts g MAPLHGRstd. Stanttrd MAPLHGR Lmts 2 0 53 5 0.48 l Fa 25% > P : No Themd Umts Mcretomg Required g *

No Umts Specdad 3e.4- ; O 40 S 0.35 Fa 25% s P < 30%: MAPFAC(P) . 0.53 + 0.01 (P . 30%)

o . .

For s f&. Core Flme ec * *

> 60% Flow N f MAPFAC(P) . 0.40 + 0.01 (P- 30%)

2 o.a - ; ; For > 60% Core Flow l l Fcr 30% s P : MAPFAC(P) = 0.64 + 0.004143 (P .100%)

l :

l l 0 10 20 30 de 50 60 70 se to 100 Power (% Rated)

J

PECO Nuc1ccr Fuol & S0rvicO3 Division PECO-COLR-L1R7 l L1R7 Cero OpOrating Limito ROport Paga 18, R5v. 1 1

FIGURE 11 FLOW DEPENDENT MAPLHGR MULTIPLIER MAPFAC(F) ]

THIS FIGURE IS VALID FOR ALL OPERATING DOMAINS i

THIS FIGURE IS REFERRED TO BY TECHNICAL SPECIFICATION 3.2.1 l t.t Note: MAXIMUM FLOW represents appropriate Recirc Pump MG Set Scoop Tube Mechanical Stop of Table 6 (this COLR)

1. 0 -

h MAXIMUM FLOW = 109%

l 0 88-I MAXIMUM ^! LOW = 114%

m I

c 0.0 4

MAPLHGR(F) = MAPFACf

MAPLHGRstd MAPLHGRstd = STANDARD MAPLHGR LIMITS

{

j ' MAPFACf(F) = MINIMUM (1.0, Af

Wc/100 + Bf) h a: We = % RATED CORE FLOW l 0

AND Af, Bf ARE CONSTANTS GIVEN BELOW:

5,0.0 g- MAX. CORE FLOW (% RATED) Af Bf 109.0 0.6778 0.4430 114.0 0.6839 0.4060 1

0.5 - '

O.4 to '33 30 40 50 60 70 00 90 100 110 Core Flow (% Rated)

v

~

5-PECO Nuc1ccr Fuol & SorvicGC Division PECO-COLR-L1R7 L1R7 COro'OpOrating Limits Report Paga 19, Rtv. 1

, TABLE 1 OPERATING LIMIT MINIMUM CRITICAL POWER RATIO (OLMCPR)

. Use in conjunction with Figures 12, 13, and 14.

2

This table is valid for two-loop operation.

Add 0.02 to the OLMCPR when in Single Loop Operation.

This table is valid for all Cycle 8 fuel types.

.* 'This table is referred to by Technical Specification 3.2.3.

TBV In Service TBV Out of RPT Out of Service and Service i- RPT'In Service Opt. B Opt. A Opt. B Opt. A Opt. B Opt. A (Taum0) (Tau =1) (Tau =0) (Tau =1) (Taus0) (Tau =1)

BOC TO EOR - 1.31 1.34 1.37 1.40 1.39 1.44 2000 mwd /ST EOR -

2000 1.35 1.38 1.42 1.45 1.43 1.51 mwd /ST to EOC Notes:

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

2. Applicable domains for this table are: RCF, ICF, MELLL, FWHOOS, FWTR, RPTOOS, TBVOOS, and SLO (with corrections as discussed above).

y--+

s PECO NuclCar Fuol & S0rvicOc Divicion PECO-COLR-L1R7 4 L1R7 Corm Op3 rating Limita Rcport POg3 20, R2.v . 1 4 FIGURE 12 POWER 73 PENDENT MCPR LIMIT ArJUSTMENTS AND MULTIPLIERS THIS FIGURE IS VALID POR THE RCF, ICF, MELLL, FWHOOS, MiD FUTR OPERATING DOMAINS THIS FIGURE IS REFERRED TO BY TECHNICAL SPECIFICATION 3.2.3 3.0 7g OPERATING LIMT MCPfkP)-Kp'CPERATING LMT MCPR(100) 2.s. } FOR P < 26% : NO THERWL LIMT NONITORNG REQUtRED 212 NO UMTS SPEOFiEO

! 2.s. '

FOR 2S% s F < Ptmas. (Ptwas -30%)

Ko = (Kbyp + 0.032 (30% P)} / OLMCPR(100)

R45 l E 2.4- KtW = 229 FOR s 60% CORE FLOW

V g '

, = 2.72 FOR > E0% CORE FLOW

60% Flow: 23 2.2 . . FO9 30% s P < 45%- Kp = 128 + 0.0134 (45% P)'

{

o @W . .

3N : FOR 45% s P < 60%: Kp = 1.15 + 0.00867(0-% P) o B 2.0- l :

E .

FOR60% s P: 40 = 1.0 + 0.00375(10(/5 P)

ABSOLLEE , ,

_ $ **' MULTIPLIER .: :

~

3 : :

.g 1. . - :

4 m

ig : .

.e s.o : :

h "g^8 2 1 .2 :

3e :

E 1., -

i 0 10 20 30 40 50 so to to 9e 100 Power (% Rated)

l

', t PECO Nuc1 Car Fuci & SOrvicOc Divicion PECO-COLR-L1R7 l L1R7 Coro Op3rcting Limito R pert Paga 21, R0v. 1 l

l FIGURE 13 POWER DEPENDENT MCPR LIMIT ADJUSTMENTS AND' MULTIPLIERS THIS FIGURE IS VALID FOR RPTOOS AND/OR TBVOOS OPERATING DOMAINS THIS FIGURE IS REFERRED TO BY TECHNICAL SPECIFICATION 3.2.3 3.0 3.

3.s .

OPER4 TING UMT KPR (P) = Kp

OPERATING UMT ICPR (100) 2.4 FOR P < 25%: NO THERMAL UM'." AONITORING REQUIRED 3 36

> (;(yy. Flow l NO UMTS SPECIFIED 7* '

FOR 2t% s P < RMrss: (Ptgass = 30%)

Kp = [Kbye + 0.064(30% P)] / OLM',PR (1001 "E 2R' E vt 2.e . j Kbyp= 2.45 Fa s 60% CORE FLOW Kbyp = 3.3G For > 60% CORE FLOW

[ 2.6 -

d B 2,, . 2.45 FOR 30% g P < 45% Kp = 1.28 + 0.0134 (45%. P) s 2.2 -

a. d .

l l

FOR 4S% s P < t'0%: Kp = 1.15 + 0.00067 (60%. P) g 8

l l FOR 60% s P Kp = 10 + 0.00375 (100%. P)

E ABSOLUTE j j MULTIPLIER j e 1. s . l l a g * '

Eu ! s'N 1 .2 -

N

, *s !.

1. 0 $

E O 10 20 30 40 50 60 70 40 90 100 Power (% Rated) i

PZCO NucicOr Fuol la SOrvicOO DiviGion

P2CO-COLR-L1R7

_L1R7 Cora OpOrating LimitG RCp3rt POg3 22, rov. 1 FIGURE 14 FLOW DEPENDENT MCPR LIMITS MCPR(F) l THIS FIGURE IS VALID FOR ALL OPERATING DOMAINS (INCLUDING SLO AND TWO RECIRCULATION LOOP OPERATION)

THIS FIGURE IS REFERRED TO BY TECHNICAL SPECIFICATION 3.2.3 3.0

- - ' FOR We (*/. RATED CORE FLOW) < 40% FOR We (% RATED CORE FLOW) 2.40%

MCPR(F)-[(Af

Wc/100 + Bf)

MCPR(F)- MAX (1.26, Af .' We/100 + Bf)

(1+ 0.0032(40-Wc)]

. l

' \

1. s -

i MAX FLOW (% of rated) Af Bf 109 -0.620 1.797

,,,, 114 -0.643 1.855 MAXIMUM FLOW = 114.0%

g 1.s-3 a

MAXIMUM FLOW = 100.0%

W 3,, . Note: MAXIMUM FLOW represents appropriate Recire Pump MG Set Scoop Tube Mechanical Stop of Table 6 (this COLR) 1,4 <

1. 3 -

4 b3-I l

1,1 0 10 30 30 49 50 se 76 se se 100 110 Core Flow (% Ratod)

j .

! ^

P!CO NucleOr Fu31 & SOrvic2O Divicion PECO-COLR-L1R7 L1R7 Caro Oper0 ting Limito Report Ptg3 23, Rsv. 1 TABLE 2 ,

ROD BLOCK MONITOR DATA Nominal Trip Setpoint Allowable Value LTSP 117.1 % 118.3 %

ITSP 112.3 % 113.5 %

HTSP 107.3 % 108.5%

DTSP 92 % 89 %

These setpoints are based on an RWE Rated MCPR limit of 1.31 and are conshtent with an RBM filter time constant between 0.1 seconds and 0.55 seconds.

LTSP - Low trip setpoint ITSP- Intermediate trip setpoint HTSP- High trip setpoint DTSP- Downscale trip setpoint

PECO NuclOtr Fu31 & S;rvic0D Divicien PECO-COLR-L1R7 L1R7 Coro Oper2 ting Limito R port Pago 24, RIv. 1 l l

\

TABLE 3 MAPLHGR SINGLE LOOP OPERATION (SLO) REDUCTION FACTOR SLO reduction factor = 1.00 for all Cycle 8 fuel types.

1 TABLE 4 I Linear Heat Generation Rate Limits i

Fuel Tvoe Maximum LHGR (kW/ft)

GE13 14.4 GE11 14.4 GE6 13.4 ,

NOTE: The LHGR is an exposure dependent value. Due to the proprietary r.ature of these values, only the maximum LHGR for each fuel type is provided in Table 4. The LHGR data is provided in Reference 5. (GE proprietary).

l t

l l

1 ..

l l

i PECO Nucicer Fu01 & S rvic 9 Division PECO-COLR-L1R7 i L1R7 Caro OperOting Limito Report P2g3 25, Riv. 1 !

I 4

TABLE 5 )

1 j

TURRINE BYPASS VALVE PARAMETERS i

i TURBINE BYPASS SYSTEM RESPONSE TIME )

Maximum delay time before start of bypass 0.10 sec valve opening following generation of the turbine oypass valve flow signal j Maximum time after generation of a turbine' O.30 sec bypass valvo flow signal for bypass valve

< position to reach 80% of full flow (includes the above delay time) 1 MINIMUM REQUIRED BYPASS VALVES TO MAINTAIN SYSTEM OPERABILITY l

Number of valves = 7 i

l

e PECO Nucisar Fual & Ssrvicas Division PECO-COLR-LlR7 LlR7 Coro Opgrating Limits Rrport Pega 26, Rsv. 1 TABLE 6 Recirculation Pump Motor-Generator (MG) Set Scoop Tube Stops Recirculation MG Recirculation MG MAPFAC(F) Curve MCPR(F) Curve Mechanical Stop Setpoint Electrical Stop Setpoint Maximum FLOW = Maximum FLOW =

(% Rated Core Flow) (% Rated Core Flow) (figure 11, this COLR) (figure 14, this COLR) 109 107 109 109 TABLE 7 Control Rod Block Instrumentation Reactor Coolant System Recirculation Flow Upscale Trip:

Nominal Trip Setpoint s 113.4%

Allowable Value s 115.6%

i

ML20198C715

Text

SUMMARY

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