ML20249B356

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Rev 0 to PECO-COLR-L1R7, COLR for LGS Unit 1 Reload 7,Cycle 8
ML20249B356
Person / Time
Site: Limerick Constellation icon.png
Issue date: 05/07/1997
From: Carmody J, Hoffman C, Mchale J
PECO ENERGY CO., (FORMERLY PHILADELPHIA ELECTRIC
To:
Shared Package
ML20249B353 List:
References
PECO-COLR-L1R7, PECO-COLR-L1R7-R, PECO-COLR-L1R7-R00, NUDOCS 9806220355
Download: ML20249B356 (26)
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PECO Nuclear Fuol & S rvices Division PECO-COLR-L1R7 l .3 L1R7 Coro Operating Limits Report Page 1, Rev. O CORE OPERATING LIMITS REPORT FOR LIMERICK GENERATING STATION UNIT 1 REICAD 7, CYCLE 8 Prepared By:_ __fd~ ~._ _ Date:

, 5~/7/9 6 Christopher K. Hoffman Engineer Reviewed By: # .hth Date:

f)7 9[f G

John La. McHale Independent Reviewer Approved By Date: d~

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James M. Carmody Manager Nuclear Design & Materials Branch 9906220355 990617 PDR ADOCK 05000352 P PM ,

b PECO Nuclctr Funi & S rvicOs Divicion PECO-COLR-L1R7 LlR7 Coro Operating Limits Report Page 2, Rev. 0 LIST OF EFFECTIVE PAGES Page(s) Revision 1 - 26 0

PECO Nucimar Fuel 6 Services Division PECO-COLR-L1R7 L1R7 Core Op vating Limits Report Page 3, Rev. 0 INTRODUCTION AND SUMh73Y.

l This report provides tne following cycle-specific parameter limits for Limerick Generating Station Unit 1 Cycle 8:

  • Maximum Average Planar Linear Heat Generation Rate (MAPLHGR)

Minimum Critical Power Ratio (MCPR)

  • ARTS MCPR thermal limit adjustments and multipliers
  • ARTS MULHGR thermal limit multipliers
  • Rod Block Monitor (REM) data e MAPLHGR single loop operation (SLO) reduction factor Linear Heat Generation Rate (LHGR)
  • 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 EM-300.

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

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

  • Increased Core Flow (ICF) up to 110% of rated core flow Feedwater Temperature Reduction (F%TR) up to 105 F during cycle extension operation

Further information on the cycle specific analyses for Limerick 1 Cycle 8 and their associated operating domains is available in References 2, 15 and ~7 Additional information on the inputs used in performing the Limerick 1 Cycle B specific analyses are available in References 3 and 4.

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PECO Nuclear Fuel & Services Division PECO-COLR-L1R7 L1R7 Core Operating Limits Report Page 4, Rev. 0 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 8. These figures are used when hand calculations are required as specified in Technical Specification 3.2.1. The MAPLHGR limit curves of Figures 1 through 8 were generated from References 5 nrough 8.

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.

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 domains. Information regarding the treatment of these MCPR limits for SLO is also provided.

Bounding MCFR values are also provided for inoperable Recirculation Pump Trip (RPTOOS) and/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 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.

dependent The flow-multiplier MMFAC (F) and flow-dependeat 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 MAPLHGR multipliers for with- and without-EOOS conditions. Also, there are two sets of power-dependent MCPR adjustments and multipliers for with- and without-ECOS conditions.

The power dependent MAPLHGR multipliers and power dependent MCPR adjustments / multipliers are sufficiently generic to permit both two recirculation loop operation and SLO in the operating domains specified.

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

PECO Nuclear Fuel & Services Division PECO-COLR-LlR7 LlR7 Core Operating Limits Report Page 5, Rev. 0 The ARTS adjustments and multipliers are shown in Figures 9 through 14. Thermal limit monitoring must be performed with the more limi' ting 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 cf 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 recirculation pump trip is inoperable, then the MCPR, MCPR (P) and MAPFAC(P) limits for Recirculat'.on Pump Trip Out Of Service (RPTOOS), must be used. Further information about the RPTOOS condition is available in References 9 and 11.

l 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 i

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PECO Nuclear Fuel & Services Division PECO-COLR-L1R7 L1R7 Core Operating Limits Repart Page 6, Rev. O settings of these stops may he 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. Further information 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 COOIANT 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 Juch 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 Station Unit 1 Reload 7 Cycle 8", General Electric Company Document No. J11-03191SRLR, Rev. O, March 1998.
3. Letter, 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 Resolved 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 Document No. J11-03191 MAPL, Rev. O, March 1998 (GE proprietary).

l

6. " Lattice Dependent MAPLHGR Report for Limerick Generating Station Unit 1 Reload 6 Cycle 7", General Electric Company Document No. 24A5185AA, Rev. O, January 1996 (GE proprietary) .
7. " Lattice Dependent MAPLHGR Report for Limerick Generating Station Unit 1 Reload 5 Cycle 6", General Electric Company Document No. 23A7232AA, Rev. 1, July 1995 (GE proprietary) .

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5 .

d PECO Nuclear Fuel & Services Division PECO-COLR-L1R7 L127 Core Operating Limits Report Page 7, Rev. 0

8. " Lattice Dependent MAPLHGR Report for Limerick Generating Station Unit 2 Reload 2 Cycle 3", General Electric Company Document No. 23A7200AR, Rev. 3, Ju-ly 1994 (GE proprietary) .

l 9 " Maximum Extended Load Line Limit and ARTS Improvement Program Analyses for Limerick Generating Station Units 1 and 2", CE Nuclear Energy Document No. NEDC-32193P, Rev.2, October 1993.

10. Letter, I: . V. Kumar to K. M. McGinnis, " Limerick ARTS Application with Equipment Out-of-Service (EOOS ) ", Dec. 10, 1993.
11. Letter, R. M. Butrovich to J. M. Carmody, " Revised Limerick 1 Cycle 8 ARTS Thermal Limits Curves", March 12, 1998.
12. " Power Rerate Condition Setpoint Calculations for the Philadelphia Electric Company Limerick Generating Station Units 1 & 2", GE Document No. GE-NE-208-20-0993-2, August 1994.
13. "GE NSSS Setpoints Required to Support Power Rerate", PECON Calculation No. LE-0082, July 27,1995.
14. " Safety Review for Limerick Generating Sts. tion Units 1 and 2, 110% Increased Core Flow Operation and Final Feedwater Temperature Reduction", GE Nuclear Energy Document NEDC-32224P, Fev. 1, October 1994.
15. Letter, R. M. Butrovich to K. W. Hunt, " Limerick 1 Cycle 7 Exposure", April 6, 1998.
16. Letter, P. M. Butrovich to K. W. Hunt, "MCPR(P) Curves for SLO du;ing 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, 1998. ,

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18. Letter, J. L. Casillas to G. C. Storey, " Applicability of Flow MCPR Limit to Single Loop Operation", May 5, 1998.

,. PECO Nuclear Fuci & Cervices Divicien PECO-COLR-L1R7 L1R7 Core Operating Limits Report Page 8, Rev. 0 l FIGURE 1 M.XIMUM AVERhCE PLide.R LINEAR HEAT GENERATION RATE (MAPLHGR) VERSUS AVERAGE PLANAR EXPOSURE FUEL TIKE MCTB404-14GZ (GE13)

THIS FIGURE IS REFERRED TO BY TECHNICAL SPECIFICATION 3.2.1 13A

,u sw si.e l

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N 1 9.. N u N "N hl 7.s x I u  !

l 3.0 5.9 10.0 15.0 20A 25A 3eh 35A 40.0 45A sea 55.0 SOA

) AVERAGE PLANAR EXPOSURE (GWd/ST) l l

l

' Avg Plan Avg Plan Avg Plan Exposure MAPLHGR Exposure MAPLHGR Exposure MAPLHGR (GWd/ST) (kwm) (GWd/ST) (kw/ft) (GWd/ST) (kw/ft) 0.0 10.53 10.0 12.12 40.0 8.96 j 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 i 8.0 11.90 35.0 9.58

s PECO Nuclear Fuc1 & Cervices Division PECO-COLR-L1R7

, L1R7 Core Operating Limits Report Page 9, Rev. 0 FIGURE 2 MAXIlf.24AVERAGEPLANAkLINEARHEAT GENERATION RATE (MAPLHGR) VERSUS AVERAGE PLANAR EXPOSURE FUEL TYPE P9 CUB 384-12GZ (Gell)

THIS FIGURE IS REFERRED TO BY TECHNICAL SPECIFICATION 3.2.1

.13.o 12.o--

11.o - -x- '

N,\

j to.o

~

l s.o N s.o

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7.o N-N s.o c.o s.o 1o.0 1s.o 20.0 as.o so.o ss.o 40.0 4s.o so.o ss.o ca.o AVERAGE PLANAR EXPOSURE (GWd!ST)

Avg Plan Avg Plan Avg Plan Exposure MAPLHGR- Exposure MAPLHGR Exposure MAPLHGR (GWd/8T) (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 1 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 i

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PECO Nuclear Fus1 & S5rvices Divicion PECO-COLR-L1R7

, L1R7 Core Operating Limits Report Page 10, Rev. 0 FIGURE 3 MAXIMLN AVERAGE PIANAR LINEAR HEAT GENERATION RATE (MAPLHGR) VERSUS .

AVERAGE PLANAR EXPOSURE EUEL TYPE P9 CUB 331-9G').O (GE11-LGS 1 Reinsert)

THIS FIGURE IS REFERRED TO BY TECHNICAL SPECIFICATION 3.2.1 s o.e u.o f

  1. ! \

g  % -I h

I so.e e.e 1 N x N

e.e \

'x 7.e s.e e.e s.e us is.e n.e na n.e na aos es.o n.e sem n.e JWerage Planer Exposure (St$/ST)

Avg Plan Avg Plan Avg Plan Exposure MAPLHGR Exposure MAPLHOR Exposure MAPLHGR (GWd/ST) (kwm) (GWd/ST) (kwm) (GWd/ST) (kwm) 0.0 11.76 12.5 12.67 35.0 9.95 2.0 12.01 15.0 12.39 40.0 e '40 4.0 12.16 17.5 12.08 45.0 8.62 6.0 12.32 20.0 11.77 50.0 7.90 l.

8.0 12.49 25.0 11.17 55.0 7.16 l l 10.0 12.67 30.0 10.57 58.7 6.52 I l-I

PECO Nuclcar Funi & S2rvice3 Division PECO-COLR-L1R7

, L1R7 Core Operating Limits Report Page 11, Rev. O FIGURE 4 MAXIMuti AVERAGE PLANAR LINEIR HEAT GENERATION RATE (MAPLHGR) VERSUS AVERAGE PIANAR EXPOSURE FUEL TYPES: P8CIB219-4GZ-100M and P8CIB219-4GZ-80M (GE6)

THIS FIGURE IS REFERRED TO BY TECHNICAL SPECIFICATION 3.2.1 13.0 110 11.0 E to.O 1_

u sa 7.0 l

4.0 (LO Le itLO 110 30.0 35.0 atLO 35.0 AVERAGE PLANAR EXPOSURE (OWd/ST)

Avg Plan Avg Plan Avg Plan Exposure MAPuiGR Exposure MAPLHGR Exposure MAPLHGR (GWd/ST) (kwm) (GWd/ST) (kwm) (GWd/ST) (kw/R)

O.0 11.90 5.0 12.00 20.0 11.80 0.2 11.90 10.0 11.90 25.0 11.60 l 1.0 11.90 15.0 11.90 30.0 11.20 l l

4 PECO Nuclear Funi & Servicas Division PECO-COLR-L1R7

, L1R7 Core Operating Limits Report Page 12, Rev. 0 FIGURE 5 MAXIMUM AVERAGE PLAl&Jt LINEAR HEAT GENERATION RATE (MAPLHGR) VERSUS AVERAGE PLANAR EXPOSURE EUEL TYPE P8CIB176-4GZ-80M (GE6)

THIS FIGURE IS REFERRED TO BY TECHNICAL SPECIFICATION 3.2.1 13.0 -

i 12.0 11.0 l l

{ 10.s e

s.0 i

s.0 7.0 s.0 0.0 5.0 10.0 15.0 20.0 25.0 30.0 35.0 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 11.80 5.0 12.00 20.0 11.90 02 11.80 10.0 12.00 25.0 11.70 1.0 11.90 15.0 12.00 30.0 10.80

PECO Nuclear Funi & Servicas Division PECO-COLR-L1R7

, L1R7 Core Operating Limits Report Page 13, Rev. O FIGURE 6 MAXIMUM AVERAGE PLANAR LINEAR HEAT GENERATION RATE (MAPLHGR) VERSUS AVERAGE PLANAR EXPOSURE FUEL TYPE P9CTB412-13GZ (GE13)

THIS FIGURE IS REFERRED TO BY TECHNICAL SPECIFICATION 3.2.1 ss.o 12.o # '

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11.o r ,

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( to.c 5 i N I g s.o N

" \ls 7.o x

s.o I o.o s.o 10.o ts.o 20.o 25.0 so.o ss.o 4o.o 4s.o so.o ss.o so.o AVERAGE PLANAR EXPOSURE (GWd/sT)

Avg Plan Avg Plan Avg Plan Exposuie MAPLHGR Exposure MAPLHGR Exposure MAPLHGR (GWd/ST) (kw/ft) (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 60.0 7.76 5.0 11.65 17.5 11.88 55.0 7.06 6.0 11.78 20.0 11.58 57.9 6 63

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PECO Nuclear Fu:1 & S rvices Division PECO-COLR-L1R7

, L1R7 Core Operating Limits Report Page 14, Rev. 0

. , FIGURE 7 l

I MAXIMt.H 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 13.o l

tz.o O '

ti.e f '

f o.o \

E \

l l s.o N '

1 s.o \N 1.o

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s.o c.o s.o so.o is.o 2o.o 2s.o so.o ss.o 4o.o 4s.o so.o ss.o so.o AVERAGE PLANAR EXPOSURE (GWdl8T)

I l Avg Plan Avg Plan Avg Plan l Exposure MAPLHGR Exposure MAPLHGR Exposure MAPLHGR l (GWd/ST) (kw#t) (GWd/ST) (kw#t) (GWd/ST) (kw#t) 0.0 10.76 7.0 11.90 25.0 10.95 0.2 10.83 8.0 12.01 30.0 10.33 1.0 10.97 9.0 12.11 35.0 9.71 2.0 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 l 6.0 11.78 20.0 11.58 57.9 6.63 l

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  • l PECO Nuc1CCr Fuol & SrrvicGo Divicion PECO-COLR-L1R7

, L1R7 Core Operating Limits Report Page 15, Rev. O l FIGURE B MAEIMUM AVERAGE PLANAR LINEAR HEAT GENERATION RATE (MAPLHGR) VERSUS AVERAGE PLANAR EXPOSURE FUEL TYPE P9 CUB 354-12GZ2 (GE11-LGS 2 Reinsert)

THIS FIGURE IS REFERRED TO BY TECHNICAL SPECIFICATION 3.2.1 110 ste /%-

11.0 ,

10.0 N

1

< SA E

N ^

s.0 \

\

7.0 i x 6.0 0.0 5.0 10.0 iLO 20.0 210 30.0 SEO 40.0 450 50.0 SLO 64.0 Average Manar Esposwo (GWWST)

JWg Plan JWg Plan JWg Plan Mr-M ERPUER Wm SEPHER 1 Pup w re WWfJER (GMt1/sT) Omr/ft) (Gett/sT) Omr/ft) (ett/sT) Omr/ft) 0.0 11.05 7.0 11.98 25.0 10.89 0.2 11.09 8.0 22.13 30.0 10.27 1.0 11.19 9.0 12.30 35.0 9.55 2.0 11.31 10.0 22.42 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

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PECO Nuclear Fusl & Scrvicas Divicion i

PECO-COLR-L1R7

, L1R7 Core Operating Limits Report Page 16, Rev. O

. FIGURE 9 POWER DEPENDENT MAPLHGR MULTIPLIER MAPFAC(P)

THIS FIGURE IS VALID FOR THE RCF, ICF, MELLL, EWHOOS AND FWTR OPERATING DOMAINS THIS FIGURE IS REFERRED TO BY TECHNICAL SPECIFICATION 3.2.1 1.2 l

l g 1.0 - p N

4 I

g 0.8 -

o 4

0.63 l 0.6 - *\ j MAPLHGR(P) = MAPFAC(P)

  • MAPLHGRatd E 0.53 g 0.55 MAPLHGReed = Standard MAPLHGR Limits g 0.4 g'( *: O.50 For 25% > P : No Thermal Limits Montomg Requred 3 No Limts Spect.ed g 0.4 -  :

E > 60% Flow  :  ; For 25% 5 P < 30% ; MAPFAC(P) = 0.55 + 0.004(P 30%)

Fors 60% Core Flow MAPFAC(P) = 0.50 + 0.004(P - 30%)

0.2 - } } For > 60% Core Flow For 30% 5 P : MAPFAC(P) = 1.0+ 0.005224(P - 100%)

0.0 i 0 10 20 30 40 50 60 70 80 90 100 Power (% Rated) l l

l l

A L__ _ ____ __ _ _ _ _ _ _ _ _ . _ . . _ . - _ _ _ . _ _ _ _ _ _ _ _ . . _ _ . _ _ _ . . _

PECO Nuclear FuOl & Sirvices Divicien PECO-COLR-L1R7

, L1R7 Core Operating Limits Report Page 17, Rev. 0 FIGURE 10 PODTER DEPENDENT MAPLHGR MULTIPLIER MAPFAC(P)

THIS FIGURE IS VALID MR RPTOOS AND/OR TBVOOS OPERATING DOMAINS THIS FIGURE IS REFERRED TO BY TECHNICAL SPECIFICATION 3.2.1 1.2 1.0 -

f g

, 0.8 -

0.84...................................................................................................

u.

0.6 -

~< 80% Flow 0. me = mace e i 3 MAPLHGRetd = !Rarerd MAPLHOR LJrres 1

,0.53 OA8 , l Fa 25% > P ; No Trumui Umts Marstonn0 Russed

.

  • No Umas Specshed 0 .4 -  : 0A0 g l g 0.35 For 25% g P < 30% : MAPFACM = 053 + 001 (P. 30%)

a  : . Fa500% CoreFkw

> 80% Flow I '.

MAPFAC(P) e 0 40 + 0 01 (P. 30%)

0.2 -

  • l Fa a 60% Coe Fkw Fa 30% 3 P : MAPF%M e 0 54 + 0004143 (P.1C0%)

0.0 0 10 20 30 40 50 60 70 80 90 100 Power (% Rated) l .j

PECO Nuclear Fuel & Services Division PECO-COLR-L1R7

_, L1R7 Core Operating Limits Report Page 18, Rev. 0 6

FIGURE 11 FIDW DEPENDENT MAPLHGR MULTIPLIER MAPFAC(F)

THIS FIGURE IS VALID FOR ALL OPERATING DOMAINS THIS FIGURE IS REFERRED TO BY TECHNICAL SPECIFICATION 3.2.1 1.1 Note: MAXIMUM FLOW represents appropriate Recirc Pump MG Set Scoop Tube Mechanical Stop of Table 6 (tnis COLR) 1.0 -

b MAXIMUM FLOW = 109%

y 0.9 - \

g MAXIMUM FLOW = 114%

\N f

d 0.8 - 4 A%PLHGR(F) s MAPFACt

b MAPLHGRstd = STANDARD MAPLHGR LIMITS A MAPFACf(F) = MINIMUM (1.0, Af

  • Wc/100 + Bf) g We = % RATED CORE FLOW g AND Af, Bf ARE CONSTANTS GIVEN BELOW.
a. 0.6 -

g MA)( CORE FLOW (% RATED) Af _ Bf 109.0 0.6778 CA430 114.0 0.6839 0.4060 0.5 -

0.4 10 20 30 40 50 60 70 80 90 100 110 Core Flow (% Rated)

i PECO Nucicar Fual & S:rvice3 Divicion .PECO-COLR-L1R7

, LlR7 Core Operating Limits Report Page 19, Rev. 0

. . TABLE 1 OPERATING LIMIT MINIMUM CRITIC ^L POWER RATIO (OLMCPR)

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

  • This table is valid for two-loop operation.

Add 0.02. to the OINCPR when in Single Loop Operation.

  • This table is valid for all Cycle 8 fuel types.

-TBV In Service TBV Out of RPT Out of Service and 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 - 1.31 1.34 2.37 1.40 1.39 1.44 2000 mwd /ST EOR -

2000 1.35 1.38 1.42 1.45 1.43 1.51 MNd/ST l to EOC I

Notes:

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

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

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PECO Nuc1cnr FuOl & S rvices Division PECO-COLR-L1R7

, L1R7 Core Operating Limits Report Page 20, Rev. O j FIGURE 12 POWER DEPENDENT MCPR LIMIT ADJUSTMENTS AND MULTIPLIERS THIS FIGURE IS VALID EUR THE RCF, ICF, MELLL, EWHOOS, AND EWTR OPERATING DOMAINS i

THIS FIGURE IS REFERRED TO BY TECHNICAL SPECIFICATION 3.2.3 3.0

&ERATNG L54T MCPR(P) = Kp

  • CPERATNG LAST hpR (100) 2.8 - FCR P = 2s% : NO *HEFEML LAST MOM 1JWIC fECMRED

.3 mgen

  • - 2,%... _ ~=-

l Kp = pow + o.032 CID% -P)]IalhCPR(100) h2 4- , Khyp = 229 FOR

  • 00% CORE FLCW g  : = zn roR. 0% CORE FtCW

~

g",

g 22-5 Row ,

pan 3ag 3 p .43g : g,,32,.o.o334 (4,g ,p) a.

N f FOR 46% = P

  • 80% : KP" 1.15 + o.00067(60%- P) o { 2.0 ~ j { ronso%3 p: Kp = 1.o + oaxn5(100%. P) emns  :  ;

a 1.8 . .

x NULTIPLER - -

l l 1.6 -  :

z^  ! .

3 $ 1.4 - l l Em . .

$"^8 2 1.2 -

{b 1.0 E

0 10 20 30 40 50 60 70 80 90 100 Power (% Rated) l 1

i

t

^

l PECO Nuclear Fuol ts ccrvicco Divician PECO-COLR-L1R7

, L1R7 Core Operating Limits Report Page 21, Rev. 0 FIGURE 13 l l -

POWER DEPENDENT MCPR LIMIT ADJUSTTIENTS AND MULTIPLIERS j i

THIS FIGURE IS VALID POR RPTOOS AND/OR TBVOOS j OPERATING D000 LINS ~

i THIS FIGURE IS REFERRED TO BY TECHNICAL SPECIFICATION 3.2.3 3.0 3.

3.s . -

OPeuTwGuwruCPR(P)=Kp OPERATNG L54TMCPR(10Q 3,4 .

FOR P < 25% : NO T}ERMAL L54T MONTCHNG REOUF4ED

>(Def,pg , l ,O NO LENTS SPEDRED

3. 2 - l  :

l l FOR 25% s P < Pbpas. (Pbpas = 30%)

KO =1% + 0.064(30%. P)]/ OLMCPR (100)

E

..e . 2m .

W . a . . .--

W = a 6 For > 80% CORE FLOW W#

l N

. 2.s . *

, , E45 FOR305 s P<45% Kp = 1.2 + C0134 (45%. P) s F/.Fkw  :  ;

pon4ss ,pcecw: Kp = 1.ts + a00es7(e0%.P) s.-  :  ;

: FORE 0% s P Kp = 1.0 + 0 00375 (100%. P) h ABSOURE

.0 1

ETIPUE  : .

1. s - l l l

3$s.4 en I

an . .

g n,1 -

l l 2

112.0 ii 5

g 0 10 20 30 de 50 40 70 to 90 100 Power (% Rated) l l

l

PECO Nuclear Fuel & Servicos Division PECO-COLR-L1R7

, L1R7 Core Operating Limits Report Page 22, Rev. O FIGURE 14 FIN DEPENDENT MCPR LIMITS MCPR(F)

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 2.0 1*8 , FOR Wc(% RATED CORE FLOW) < 40% FOR We(% RATED CORE FLOW) > 40%

MCPR(F) * [(Af

  • Wd100 + Bf)
  • MCPR(F)= MAX (1.26, Af
  • Wd100 + Bf)

(1+ 0.0032(40-We))

1. 8 -

MAX FLOW (% of rated) Af Bf 109 -0.620 1.797 114 -0.643 1.855 MAXIMUM FLOW = 114.0%

g 1.6 -

E, o MAXIMUM FLOW = 109.0%

M 1,5 Note: MAXIMUM FLOW represents appropriate A Recire Pump MG Set Scoop Tube Mechanical Stop of Table 6 (this COLR) 1.4 -

1.3 -

1.2 -

1.1 0 10 20 30 40 50 60 70 80 90 100 110 Core Flow (% Rated)

3 .

PECO Nuclear Funi ( Servicas Division PECO-COLR-L1R7

, L1R7 Core Operating Limits Report Page 23, Rev. 0 TABLE 2 RCD BLOCK MONITOR DATA l

l Nominal Trip Setpoint l

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 consistent 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

_7_-____-______-________-____

PECO Nuclear Pael & Servic:3 Divicion PECO-CO!Jt-L1R7

, L1R7 Core Operating Lianits Report Page 24, Rev. 0 1

TABLE 3 ,

MAPLHGR SINGLE LOOP OPERATION (SLO) REDUCTION FACTOR 1

l SLO reduction factor = 1.00 for all Cycle 8 fuel types.

TABLE 4 Linear Heat Generation Rate Limits l

Fuel Tvoe Maximum LHGR (kW/ft)

GE13 14.4 l GE11 14.4 GE6 13.4 NQTE: The LHGR is an exposure dependent value. Due to the proprietary nature 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 l

l

t PECO Nuclear Fuel & S3rvicen Division PECO-COLR-L1R7

, L1R7 Core Operating Limits Report Page 25, Rev. O s

TABLE 5 .

TUR8INE BYPASS VALVE PARAMETERS TURBINE BYPASS SYSTEM RESPONSE TIME Maximum delay time before start of 0.10 sec bypass valve opening following generation of the turbine bypass valve flow signal Maximum time after generation of a 0.30 see turbine bypass valve flow signal for bypass valve position to reach 80% of full flow (includes the above delay time)

MINIMUM REQUIRED BYPASS VALVES TO MAINTAIN SYSTEM OPERABILITY Number of valves = 7 l

l l

)- NECONuclearFuni&SorvicesDivision PECO-COLR-L1R7

( L1R7 Core Operating Limits Report Page 26, Rev. 0 TABLE 6 l

Recirculation Pump Motor-Generator (MG) Set Scoop Tube Stops Recirculation MG Recirculation MG MAPFAC(F) Curve Mechanical Stop Setpoint MCPR(F) Curve 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%

_ - _ _ _

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