ML20195B302

Rev 0 to PECO-COLR-L2R5, COLR for Lgs,Unit 2 Reload 5 Cycle 6

ML20195B302
Person / Time
Site:	Limerick
Issue date:	05/06/1999
From:	Hull G, Mchale J, Robert Wolfgang PECO ENERGY CO., (FORMERLY PHILADELPHIA ELECTRIC
To:
Shared Package
ML20195B299	List: ML20195B295 ML20195B302
References
PECO-COLR-L2R5, PECO-COLR-L2R5-R, PECO-COLR-L2R5-R00, NUDOCS 9905280218
Download: ML20195B302 (28)

Text

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't PECO Nu21 ear, Fuel & S rvicO3 Divioicn PECO-COLR-L2R5 L2R5 Care Operating Limito Report P2ge 1, Rev. 0 CORE OPERATING LINITS REPORT FOR-LIMERICK GENERATING STATION UNIT 2 RELOAD 5, CYCLE 6 Prepared By: # m 0A. / Date: O)3!99 John.La. McHale I /

Engineer Reviewed By: .

//h tr/ Date: T/99 Rdbert f.(XJolfgang ' '

Independent Reviewer Reviewed By: m Date: 97 d George R. Hull # '

Independent Reviewer Approved By I/'[I C/W Date: E NF V' James M & armody Manager

Juclear Design - BWR Branch 9905280218 990520 C PDR ADOCK 05000353 )

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PECO Nu21 ear, Fu3i & S rvic00 Divicion l P~CO-COLR-L2R5 L2R5 Caro Oper!. ting Limits R0 port Page 2, Rev. O i LIST OF EFFECTIVE PAGES Page(s) Revision 1-28 0 i

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• k PRCO' Nuclear, Fu21 & S0rvic;3 Divicion PECO-COLR-L2R5 L2R5 C ro OperCting Limita Report Page 3, Rev. O INTRODUCTIDN AND

SUMMARY

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This report provides the follcwing cycle-specific para .eter limits f:r Limerick Genera:Ing 2:stien Unit 2 Cycle 6:

• Maximum Average Pla- cr Linear Heat Generation Rate (MAPLHGR)

Minimum Critical Fower Ratio (MCPR)

ARTS MCPR thermal limit adjustments and multipliers ARTS MAPLHGR thermal limit multipliers Rod. Block Monitor 'RBM) setpoints

• MAPLHGR single '.ccp operation (SLO) reduction fa::or

• Linear Heat Generation Rate (LHGR)

• Turbine Bypass "alve parameters

• Recirculation Fu p Motor Generator (MG) Set Scoop Tube Stops

• Reactor Coolan System Recirculation Flow Upscale Trips These values have been determined using NRC-approved methodology,

' Reference 19, and are established such that all applicable limits f the plant safety analys:.s are met.

This report is submitted in accordance with Technical 5pecification

f. .l.9 of Reference .

Preparat:.cn of this report .;as performed in accordance with PECC ::uclear, Fuel & Services Division Procedure T.4-200.

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

• Maximum Extended ' cad Line Limit IMELLL) do'c. :o 81% of rated core ficw during full power operaticn

• Increased Ccre F'. w (:CF) up to 110% of rated ::re flow

• Feedwater Temperature Reduction (FWTR) up :: :5 F during cycle extens.:n :peration

• Feedwater Heater Out of Service ( F"WHOOS ) ;p :o 60 F feedwater temperature reduction at any time furing the cycle prior Oc cycle extension.

MAPLHGR LIMITS The limiting MAFLH3R value for the most limi .ng lattice excluding natural uran:.um) of each fuel type as a function of average planar exposure is given in Figures 1 through E. References 3, 4, 5 and 6. These figures are used when hand calculations are required as specified in Technical Specification 2.2.1. ,

j For single loop Operation, a reduction f actor s used which is shown in Table 3 (Reference 13). {

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• PECO Nuclccr, Fuol & S rvic33 Divicion PECO-COLR-L2R5 L2R5 Ccro Operating Limito Rep 3rt P2g3 4, Rev. O i MCPR LIMITS-l The' MCPR value for use in Technical Specification 2.2.3 for 1 I

each fuel type is given in Table 1, Reference 2. This table is l valid for all Cycle 6 fuel types and operating nomains. l Inf0r.ation regarding the treatment of these MCPR limits for SLO is also provided.

Sounding MCPR values are also provided for incperable Rec:.rculation Pump Trip (RPTOCS) or inoperable Steam Eypass System (TEV225). These two options represent the Equipment Out of Service (ECCS; condition.

ote that in Table 1 the term " EOR" refers to the cycle exposure at which operation at " rated conditions" is no longer poss:.hle (i.e., the cycle exposure at which cycle extension beg ns). The cycle exposure which represents " EOR" is given in the lates: verified and approved Cycle Management Report. This value can :hange 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 adm n:.stration of the MCPR and MAPLHGR thermal limits. The flow-dependent adjustment MCPR(F) :s sufficiently generic : apply to all fuel types and operating domains, Reference 18. However. there <

are : 0 sets of flow-dependen: MAPFAC(F) multipliers f:r dual-loop and s ngle-loop operation, References '8 and 11, respectively. In addi::.:n , there are also two sets of power-dependent :GPLHGR multi;;.ers for with- and withcut-EOOS conditions, References 9 and 7, respectively. Finally, there are two sets of power-dependent MCFR adjustments and multipliers for with- and  :::hout-EOOS cond:.n:ns, Reference 11.

!hese adjustments and multipliers are shown in Figures 9 thr:uph ' 5. Thermal limit monitoring must be performed c h the

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more _ :::ing MCPR and MAPLHGR limits resulting f rom the p:wer- and ficw-nased calculation.

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ROD BLOCK MONITOR SETPOINTS The ARTS RBM provides for power-dependent RBM trips. The trip setp: nts/ allowable values and applicable RBM signal filter time constan: data are shown in Table 2. These 'calues are f:r use with Tecnn . al Specification 3.3.6. The use of the setpoints specified in Table 2 is documented in References 2, 9, 10, and 14.

LINEAR HEAT GENERATION RATES l The maximum LHGR value for each fuel type for use .n Te::.a.ical Spe:. fica: ion 3.2.4 is given in Table 4. The LHGR is an exposure dependen: value. Due to the .treprietary nature of these calues only ne maximum LHGR for each fuel type is listed in Table ,. The LHGR data is listed in References 2 & 4 (GE proprietary

PECO NucicCr, Fual & ScrvicOO Divi 0 ion PECO-COLR-L2R5 L2RS Coro Oper ting Limito Report Page 5, Rev. O 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 :.n Table 5, Reference 12. If these requirements cannot be met , the MCPR, MCPR(P) and MAPFAC(P) limits for inoperable Steam Bypass System, known as Turbine Bypass Valve Cut Of Service (TBVOOS), must be used.

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

RECIRCULATION PUMP MOTOR-GENERATOR (MG) SET SCOOP TUBE STOPS The electrical and mechanical s cps are set to limit the reactor core :colant flow rate during an event in which the recirculation ficw rate increases to its maximum value.

Specification Eurveillance Requirement number 4.4.1.1.2 Technical requires that each pump MG set scoop tube mechanical and electrical step shall be demonstrated OPERABLE, with cverspeed 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. 1 I

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CONTROL ROD BLOCK INSTRUMENTATION REACTOR COOLANT SYSTEM RECIRCULATION FLOW UPSCALE TRIP Technical Specification Limiting :endition for Operat.cn number 3.3.6 requires control rod bicck instrumentation channels shall be OPE 1? with their trip setp:;nts consistent with the values shown in the Trip Setpoint column f Technical Specificat:.cn Table 3.3.6-2. The Reactor Coolant System Recirculation Flcw Upscale Trip s a cycle-specific value and as such is found in Table 7 of this COLR. Table 7 lists the Nominal Trip Setpoint and Analytical Value. These setpoints are set high enough to allow full utilicati n of the enhanced ICF dcmain up to 110% of rated core flow. Reference setpoint values used.

8 provides the current basis for the trip HIGH EXPOSURE PROGRAM BUNDLES Limerick Tnit 2 Cycle 6 is the fourth cycle of irradiation f:r four Limerick Unit 1 Reload 4 Gell fuel bundles. These bundles previously res; fed in Limerick Unit 1 Cycles 5, 6 and 7 They have spent one year in the Limerick fuel pcci and have been inspected prior to being ;nserted into this cycle. These bundles are part :f a joint 3E-FE::N Lead Test Assembly LTA) pro";rram. This LTA

PECO Nuclocr, FuOl & S0rvic00 Divicion PECO-COLR-L2R5 L2R5 C:re Operating Limito Report PCge 6, Rev. O program was implemented in order to obtain fuel bundle data at high exp.osure,s (beyond the :urrent Gell licensed limit of 70 GWd/MT Peak Pellet Exposure, Reference 17).. A PECON 10CFR50.59 Review has been performed for the use of these bundles in a fourth cycle. No Unreviewed Safety 'uestions were identified. New MAPLHGR and DESLIM limits, respectively used for calculating MAPRAT and MFLPD, have been determined by the fuel vendor and are shown in Figure 6 and Table'4. See References 2, 3, 15 and 16 for more information on these bundles. i SAFETY LIMIT MINIMUM CRITICAL POWER RATIO (SLMCPR)

The Safety Limi: Minimum Critical Power Ration (SLMCPR) for Limerick 2 Cycle 6 is 1.12 for Dual Loop Operation and 1.14 for Single Loop Operation. These values are documented in Reference 2.

REFERENCES

1. " Technical Specifications and Bases for Limerick Generating Station Unit 2", :: ket No. 50-353, License No. NPF-85.

2. " Supplemental Reload Licensing Report for Limerick Generating Station Unit 2 Rel:ad 5 Cycle 6", General Electric Company Document No. J11-:3 450SRLR, Revision 0, April 1999.

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3. " Lattice Dependen: MAPLHGR Report for L:.merick Generating 1

Station Unit 2 Reload- 5 Cycle 6", General Electric Company Document No. J11-034 BOMAPL, Revision 0, April 1999.

4. " Lattice Dependen: MAPLHGR Report for Limerick Generating I Station Unit 2 Rel:ad 4 Cycle 5", General Electric Company Document No. 24A53 33AA, Rev. O, January 1997

5. " Lattice Dependen: MAPLHGR Report for Limerick Generating Station Unit 2 :e_:ad 3 Cycle 4", General Electric Company Document No. 24 A5' ~ 5AA, Rev. O, January 1995.

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6. " Lattice-Dependent MAPLHGR Report for Limerick Generating Station Unit 2 Reload 2 Cycle 3", General Electric Company Document No. 23A72::AA, Rev. 3, July 1994.

7 Letter, G. V. K.

-?.:.ma r to M. McGinnis, " Limerick ARTS Application with Equipment Out-of-Service (EOC3)", Dec. 10, 1993.

8. " Safety Review for Limerick Generating Stat on Units 1 and 2, 110% Increased 2:re Flow Operation and Final Feedwater Temperature Redu :i:n", GE Nuclear Energy Cocument No. NEDC-32224P, Revision 1, : tober 1994.

'. PECO ' Nuclear, Fu31 & Strvicts DiviCion PECO-COLR-L2R5 L2R5:Ccr3 Oper; ting Limita R: port P ga 7, Rev. O

?. " Maximum Extended L0ad Line Limit and ARTS Improvement Program

. Analyses for Limerick Generating Station -Units ~ and - 2", GE.

j Nuclear -Energy Document No. NEDC-32193 P, ' Rev. 2, October 1993.

10. "GE NSSS Setpoints Required to Support Power Rerate", PECON Calculation No. LE-0082, Revision 5, June 19, 1998.

11. Letter, J. A. Baumgartner to'J. M. Carmody, " Limerick 2 Cycle 6 ARTS Curves", May 5, 1999.

12. Letter, R. M. Butrovich to J. M. Carmody, " Limerick 2 Cycle 6 Resolved OPL-3", December 11, 1998.

13. " Limerick Generating Station Unit 2 ECCS-LOCA Evaluation for Cycle 6", GE Nuclear Energy Document No. J11-03480-08-01P, l February 1999.

14. " Power Rerate Condition Setpoint Calculations for the Philadelphia Electric Company Limerick Generating 5tation Units l & 2", GE Document No. 3E-NE-208-20-0993-2, August 1994.

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15. Letter, J. A. Baumgartner to K. N. Hunt, " Licensing Evaluation for Core Reconfiguraticn of Limerick 2 Cycle 6", April 14, 1999.

"6.

. General Electric Report, "10CFR50.59 Safety Evaluation, Continued Irradiation of Limerick 1 Gell Assemblies in Limerick 2 Cycle 6", March 22, 1999.

! 1~. General Electric Report No. NEDE-31917P, " Gell Compliance With Amendment 22 of I'EDE-24011-P-A (GESTAR II), April 1991.

'. 3 . " ARTS Flow-Dependent Limits with TBVOOS for Feach Bottom

' Atomic Power Stati n and Limerick Generating S t a t :.on " , GENE Document NEDC-32547F, June 1998.

19.'" General Electri; Standard Application for Rea:ter Fuel".

NEDE-24011-P-A-12, August 1996.

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PECO Nuc100r, Fu31 & S0rvicOD Divicion PECO-COLR-L2R5 l L2R5 Cora Operating Limit 0 Report Page 8, Rev. O I

I Figure 1 MAXIMUM AVERAGE PLANAR LINEAR HEAT GENERATION RATE (MAPLHGR)

VERSUS AVERAGE PLANAR EXPOSURE l BUNDLE TYPE 2 (P9CTB412-13GZ1, GE13)

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

l .

i u. . . .... . ...

k l

l '

- 1

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u... . . . . .

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.... . . , .. . . '. . ... . , J l

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, t... n.. n.. .... u.. ....

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) ,LGWd/ST) (kW/ft)

C.: 10.74 7.0 11.77 25.0 10.98 ,

l 0.1 10.81 8.0 11.93 30.0 10.35  !

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. 10.91 9.0 12.10 35.0 9.73 2.: 11.04 10.0 12.22 40.0 9.10 i 3.. 11.18 12.5 12.25 45.0 s.45 4.: 11.32 15.0 12.13 50.0 7.77 E.: 11.47 17.5 11.91 55.0 ".:7 l 6.: 11.62 20.0 11.61 57.99 6.63 i

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' ". PECO Nuclocr, Fu:1 & S rvicO3 Divicien PECO-COLR-L2R5

. L2R5 Cera OperOting Limito Rep 3rt Page 9, Rev. O i l

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. . Figure 2 MAXIMUM AVERAGE PLANAR LINEAR HEAT GENERATION RATE (MAPLHGR)

VERSUS AVERAGE PLANAR EXPOSURE l

BUNDLE TYPES 3, 6 & 19 (P8CIB219-4GZ, GE6)

This Figure is Referred to by Technical Specification 3.2.1 1

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l n.. .- - . -

i.... .. . ... . ..a... .. . . . . .. .. .i.. ..

. . j ts.s . ,

c_

w <

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t 4

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a t.e , . . . ......... ... . .. ... . . . .. .

13.3 . .

. .......... ..r . ., . . . ,. .

to.o a.o ia lo.e an.s ts.s as.e ss.s 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) 0.2 11.90 10.0 11.90 25.0 11.60 1.0 ^1.90

_ 15.0 11.90 30.0 11.20 5.0 12.00 20.0 11.80

'a PECO Nuclo. r, Fu21 & SnrvicO3 Divicien PECO-COLR-L2R5 L2R5 Cara Operating Limito Report Page 10, Rev. 0 '

l Figure 3 MAXIMUM AVERAGE PLANAR LINEAR HEAT GENERATION RATE (MAPLHGR)

VERSUS AVERAGE PLANAR EXPOSURE BUNDLE TYPES 4 & 7 (P8CIB176-4GZ, GE6)

This Figure is Referred to by Technical Specification 3.2.1 a.s..- . ~

ta.s ts.s ._

=

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~ . .

st.s I

5 1 5

a .

>>.e

. '. , l no.s )

10.e s .e s.o :s.e ts.e as.e is.e so.e Aveerage 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) 0.2 11.80 10.0 12.00 25.0 11.70 1.0 11.90 15.0 12.00 30.0 10.80 5.0 12.0C 20.0 11.90 l

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PECO Nuc1 car, PuO1 & S;rvic00 Divicion PECO-COLR-L2R5 L2RS Cera Opercting Limita Report Page 11, Rev. 0 Figure fa MAXIMUM AVERAGE PLANAR LINEAR HEAT GENERATION RATE (MAPLHGR)

VERSUS AVERAGE PLANAR EXPOSURE BUNDLE TYPE 5 (P9CTB412-13GZ2, GE13)  !

This Figure is Referred to by Technical Specification 3.2.1

2. . .

13.0 .. ., .. . . ...

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it.a . .. ' . . . . . . . . . , .

g <

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g ... . . . ...

g .

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..e. . .. .. . . .

e.e . .

,.s. . . . ... . .....

a.s e.s to.e 22.s se.e es.e ts.: so.s Average Planar Exposure (GWd/ST)

Avg. Plan Avg. Plan Avg. Plan Exposure MAPLHGR Exposure MAPLUGR Exposure MAPLHGR (GWd/ST) (kW/ft) (GWd/ST) (kW/ft) (GWd/ST) (kW/ft) 0.0 10.74 7.0 11.77 25.0 10.98 0.2 10.81 8.0 11.93 30.0 10.35 1.0 10.91 9.0 12.10 35.0 9.73 2.0 11.04 10.0 12.22 40.0 9.10 3.0 11.18 12.5 12.25 45.0 8.45 4.: 11.32 15.: 12.13 50.0 7.77 5.0 11.47 17.5 11.91 55.0 7.07 6.: 11.62 20.0 11.61 57.99 6.63 l

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r PECO Nuc100r, Fuol & S rvicO3 Divi 0 ion PECO-COLR-L2R5 L2R5 Caro Operating LimitG Report P ge 12, Rev. 0 Figure 5 l

MAXIMUM AVERAGE PLANAR LINEAR HEAT GENERATION RATE (MAPLHGR)  ;

l VERSUS AVERAGE PLAPUt EXPOSURE  !

l BUNDLE TYPE 11 (P9 CUB 354-12GZ2, Gell) l This Figure is Referred'to by Technical Specification 3.2.1 i

a..

i . . .

u... .....:...... ..:. . . . .. l 1

u... . .. ... , . . ... ....... . ..

u.. . ... ... . .. . . .. .. ..

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. se.. .... 3. . . .... .... ....

l Average Planar Exposure (GWd/ST)

Avg. Plan Avg. Plan Avg. Plan Exposure MAPLHGR Exposure MAPLHGR Exposure MAPLHGR (GWd/ST) (kW/ft) (GWd/ST) (kW/ft) (GWd/ST) (kW/ft) 0.0 11.05 7.0 11.98 25.0 13.89 0.2 11.09 8.0 12.13 30.0 10.27 1.: 11.19 9.0- 12.30 35.0  :.55 2.: '11.31 10.0 12.42 40.0 5.87 3.; 11.44 12.5 12.38 45.0 s.24 4.: 11.56 15.0 12.10 .50.0 .62 5.: -11.70 17.5 11.79 55.0 .00 11.84 20.0 i

5.: 11.49 57.9 f.60 l

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. .. i as PECO NuclCSr, Fu3l & SOrvicOO Divicicn PECO-COLR-L2R5 L2R5 Cara Op3r2 ting Limits Report Pig 3 13, Rev. 0 l

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

VERSUS AVERAGE PLANAR EXPOSURE '

BUNDLE TYPE 13 (P9 CUB 331-9G5.0, Gell-High Exposure Program)

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

sa.e . . . .. . ,. . ..

n.e . ., .

se.e . .. .. .

M L <

g.... . .;

5

=

e.e . .

s .o . . .. .

..e. . .. . ... . ..

... u. .... .... .... .... .... , . . .... ;

Average Planar Exposure (GWd/ST) l Avg. Plan Avg. Plan Avg. Plan Exposure MAPLHGR Exposure MAPLHGR Exposure MAPLHGR (GWd/ST) (kW/ft) (GWd/ST) (kW/ft) (GWd/ST) (kW/ft) 0.0 9.39 8.0 9.97 35.0 9.41 0.2 9.43 9.0 10.04 40.0 9.20 1.0 9.50 10.0 10.'2

_ 45.0 8.93 2.0 3.59 12.5 10.22 50.0 8.55 3.0 9.65 15.0 1:.12 55.0 8.02 4.0 9.71 17.5 1:.:4 60.0 7.55 5.0 9.77 20.0 9.94 65.0 7.12 6.0 9.84 25.0 9.~~ 70.0 6.74

~.0  ?.90 30.0 9.59 ~2.52 6.54

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? PECO Nucicr2r, Fu3i & S rvicOS Divicion PECO-COLR-L2RS L2R5 Caro Op rating Limito Report Page 14, Rev. 0 l

Figure 7 MAXIMUM AVERAGE PLANAR LINEAR HEAT GENERATION RATE (MAPLHGR)

VERSUS AVERAGE PLANAR EXPOSURE BUNDLE TYPE 15 (P9 CUB 399-14GZ, Gell)

This Figure is Referred to by Technical Specification 3.2.1 i... l 5 2. . . .. .,. . ... .

1 io... . .

3 5. . < . .

3?

1 8 te.. . . . .

5 2 ,

... 22.. 2... .... .... .... ....

Average Planar Exposure (Guid / ST)

Avg. Plan l Avg. Plan Avg. Plan Exposure MAPLHGR ,

Exposure MAPLHGR Exposure MAPLHGR (GWd/ST) (kW/ft) I (GWd/ST) (kW/ft) (GWd/ST) (kW/ft) 0.0 10.57 7.0 11.67 25.0 10.75 0.2 10.63 8.0 11.82 30.0 10.14 1.0 '0.76

_ 9.0 11.95 15.0 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 ^1.24

_ 15.0 11.97 30.0 7.60 5.0 __.;c _s.5 11.68 55.U 6.90 6.0 I

~1.53 i 20.0 11.37 i .25 6.59

l PECO NuclOcr, FuO1 & S0rvic33 Divioicn PECO-COLR-L2R5 i L2R5 Caro Op3rOting Limita Report Page 15, Rev. 0 1

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Figure 8 MAXIMUM AVERAGE PLANAR LINEAR HEAT GENERATION RATE (MAPLHGR)

VERSUS AVERAGE PLANAR EXPOSURE BUNDLE TYPE 18 ( PS .2TB416 -15GZ, GE13)

This Figure is Referred to by Technical Specification 3.2.1 i...

ts.s < . . .' . . .

ta.e < ,. . .

l '

it.s < . ' . . . ,.

k B

i

{

$ so.s 4 . .. . .. .. . . .

5 I .

..e< .... .

i 7.9 < . .. ,

s.s t .: se.s ss.: so.o es e in.s se.e Average Planar Exposure (GWd/ST)

Avg. Plan Avg. Plan Avg. Plan l Exposure MAPLHGR Exposure MAPLHGR Exposure MAPLHGR (GWd/ST) __kW/ft)

( JGWd/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 1.3 10.73 3.0 12.04 35.0 9.74 2.0 10.90 10.C 12.16 40.0 9.11 3.0 11.09 12.5 12.18 45.0 8.46 4.: 11.30 _5.. 12.11 50.. ,.<8 5.: 11.47 17.5 11.91 55. ' 08 6.: 11.61 13.: 11.62 58.C5 6.63 l

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PECO Nuc100r, FuS1 & S;rvic;O DiviGicn PECO-COLR-L2R5 L2R5 Cora OperOting Limito Rep;rt Pcga 16, Rev. O t

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 I

1.0 j o.e.

0.e .

l 0.1 i

0.63 E 0,s . <= 60% Flow l iMAPLHGR(P) = MAPFAC(P)

• MAPLHGRstd 0.55 MAPLHGRstd - Standard MAPLHGR Umits

. 0.53 6

O.48  ; For 25% > P : No Thermal Limits Morutonng Requirea g  ; No Limits Specified I8*' > 60% Flow !  ! For 25% <= P < 30% : MAPFAC(P) = 0.55 + 0.004(P . 30%)

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I For <= 60% Core Flow 0,3 -

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{

4

{ MAPFAC(P) = 0.50 + 0.0044P - 30%)

; For > 60% Core Flow 0.2 ,

{ For 30% <= P : MAPFAC(P) = 1.0 0.005224(P .100%)

l l l l 0.2 - l l l l l l l l 0.0 0 10 20 30 40 50 60 70 to 90 100 Power (% Rated)

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!.4 PECO Nucl=r, Fu01 & S rvicO3 Divicica PICO-COLR-L2R5 L2R5 Caro Opersting Limita Report P ge 17, Rev. O FIGURE 10 I

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POWER DEPENDENT MAPLHGR MULTIPLIER MAPFAC(P) l THIS FIGURE IS VALID FOR THE RPTOOS OR TBVOOS l

OPERATING DOMAINS This Figure is Referred to by Technical Specification 3.2.1 1

1.o - _.

0. 9 -

6.e .

0.? -

5 8 O.55

c. 60% Flow i MAPLHGR(P) MAPFAC(P)

• MAPLHGRstd 1

Ee.s< l 0 53 MAPLNGRstd. Stardard MAPLHGR Umts

!f 0 48 l d

i j  ! For 25% > P : No Thermal Umts Morntonrg Required g.... {

, 0.40 No Umts Spoofied 0.35  !

For 25% c. P c 30% : MAPFAC(P) = 0 53 + 0 01(P 30%)

,,,, {  ; > 60% Flow For <= 60% Core Flow l l MAPFAC(P) = 0 40 + 0 01(P . 30%) :

; I

'>- For > 60% Core Flow I

: I l l For 30*'. c. P l MAPFAC(P) = 0 84+ 0 004143(P 100%)

0.1 < l l l l l l l .:

e..

0 10 20 30 40 50 40 70 Se De let l Power (% Rated) l

)

a 4

PECO NuclC0r, Fuci & S0rvic00 Divicien PECO-COLR-L2R5 L2R5 Cara Operating Limits Report Paga 18, Rev. 0 FIGURE 11 l

FLOW DEPENDENT MAPLHGR MULTIPLIER MAPFAC(F) )

THIS FIGURE IS VALID FOR ALL OPERATING DOMAINS I EXCLUDING SINGLE LOOP OPERATION I 1

This Figure is Referred to by Technical Specification 3.2.1 1

1.1

1. o . '

I 1

0. 9 -

E j 0.. .

j i

MAPLHGRiA . MAPFAC(F)

• MAPLHGRstd g e.7 -

g For Tvm Loco Operaton. > 70% Wr

= l MAPFACiF)- The Mnimum of EITHER 1.0 l OR {0.0268 x (Wr 70)/10 + 0.9732)

~ i For Two Loco Operaton. s 70% We f

MAPFACiF) = {0 6682 x (Wr/100) + 0.5055}

WT = % Rateo Core Flow 0.5-l 0.a 30 de le 40 70 se 90 up 100 Core Flow (% Rated)

r~" .

1 1

• • i PECO NuclT_r, FuOl & S rvic00 Divicicn PECO-COLR-L2RS

.L2R5 Cara operating Limits Report P0g3 19, Rev. O I

l FIGURE 12 FLOW DEPENDENT MAPLHGR MULTIPLIER MAPFAC(F)

THIS FIGURE IS VALID FOR SINGLE LOOP OPERATION This Figure is Referred to by Technical Specification 3.2.1

..s -

1 l

l l

l .3' l f g .. .

t I

l l e.-

1 5 1

a MAPLHGR(F) . M APFACf F * 'A APLHGRstd For Single Loop Operation.

M APFAC(F) . The Minimum of EITHER 0.79 OR (0 6682 x (WW100) + 0.5055)

.s< WT % Rated Core Flow l

.s la 40 $9 15 70 80 63 100 310 Core Flow (% Rated) l l

1 l

S PECO Nucicer, FuO1 & S3rvicO3 Division PECO-COLR-L2R5 L2R5 Coro Operating Limita Report Paga 20, Rev. 0 TABLE 1 OPERATING LIMIT MINIMUM CRITICAL POWER RATIO (OLMCPR) l Use in conjunction with Figures 13, 14 and 15.

I l

• 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 6 fuel types.  !

This table is referred to by Technical Specification 3.2.3. 1 l

I TBV In Service TBV Out of RPT Out of and Service Service RPT In Service i

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 1.32 1.35 1.35 1.40 2000 mwd /ST 1

EOR - '

2000 1.32 1.35 1.38 1.41 1.40 1.48 mwd /ST to EOC i

Notes:

1. h'he.. Tau does not equal 0 or 1. determine OLMCFE '/ia linear inter;tlation.

l l

PCCO NuclOcr, FuOl & S rvicOO Divicion PECO-COLR-L2R5 L2RS COra OperOting LimitO R port POge 21, Rev. 0 1

FIGURE 13 {

POWER DEPENDENT MCPR LIMIT ADJUSTMENTS AND MULTIPLIERS 1

THIS FIGURE IS VALID FOR THE RCF, ICF, MELLL, FWHOOS

{

AND FWTR OPERATING DOMAINS i This Figure is Referred to by Technical Specification 3.2.3 3.0 2.e- 2.83

> 60% FW OPERATING UMIT MCPR(P) = K,

• OPERATING UMIT MCPR(100) l

! 2.67 FOR P < 25%: NO THEFMAL UMIT MONITORING REQUIRED

,,,,  ;  ; NO UMITS SPECIFIED l l l- FOR 25%s P < Pm. (Pm = 30%)

5 #*

K,= [ % + 0 032(30%- P)] / OUCPR(100) 5 l l l 2.25 3***'  % = 2.25 FOR s 60% CORE FLOW y } } = 2.67 FOR > 60% CORE FLOW I

g . .

8 FOR 3W.s P c 45% : Kp = 1.28 + 0 0134(45%- P)

-2 .0< . .

g . .

a l l

.a . . FOR 45%s P c 60%: Kg = 1.15 + 0.00867(60%- P) 3 l l j 18' ' '

FOR 60% s P - Kp = 1.00 + 0 OCD75(100% P) h  !

2. s .

. s

1. a . l l l l l l l l l 2.3  ;  ;

l l l i

l l  :  !

l 1.0 0 10 20 30 40 50 50 70 80 90 100 Power (% Rated) l

l <

4 PECO NuclOOr, Fucl T. SOrvicO3 Divicion PECO-COLR-L2R5 L2R5 C.:rO OperOting Limita R p3rt P g3 22, RCv. 0

. FIGURE 14 POWER DEPENDENT MCPR LIMIT ADJUSTMENTS AND MULTIPLIERS i

THIS FIGURE IS VALID FOR THE RPTOOS OR TBVOOS I OPERATING DOMAINS This Figure is Referred to by Techical Specification 3.2.3 1

l 3.0 1

3 61 i

> 60% Flow OPERATING LIMIT MCPR(P) - Kp ' OPERATING LIMIT MCPR(100)

' l l

FOR P < 25% ; NO THERMAL LIMIT MONITORING REQUIRED

, 3.30 NO LIMITS SPECIFIED

1 FOR 25% s P < Penss . (Press - 30%) l 2.0  ;

s Ku - [ Kem + 0 062(30% - P)] / OLMCPR(100) h 2.72 Kem- 2.41 FOR s 60% CORE FLOW  !

C 160% Flow

- 3.30 FOR > 60% CORE FLOW h,,,. ,

I d FOR 30% s P < 45% .

2.41 Ko - 1.28 + 0 0134(45% - P) i  : FOR 45% s P < 60% : K, = 1.15 + 0 00867(60% P) y a.a .  ; I g FOR 60%5P: K, = 1.00 + 0 00375(100% - P) 1 .0 I

1.4 3,, ~

0 10 20 30 40 50 60 70 00 00 100 Power (% Rated) l l

l t.

t.

l

\ PECO Nuclear, Fuol & SrrvicOc Divicien PECO-COLR-L2R5 L2R5 Caro operating Limito Repsrt POge 23, Rev. 0 FIGURE 15 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 i

a.se

"' For Two Looo Operanon. SLMCPA s

• 2. g 40% W, MCPA(F) . The Maximum of E:~~EA 125 OR ( 0.5784 x 'W 100) + 1.7073}

i se + For Two Loco Operahon. SLMCPQt ' ' 2. < 4C?- W, l

MCPR(F) . ( 0.5784 x (Weit;' .17G73} x l

l ( 1 + 0.0032 s 40 - Wv)}

1.t3 i l We . % Rated Core Flow 1.se .

m I t.se 1....

l

1. se .

m. .

. 19 is se so so e en to as sie Ocre Flow (% Rated)

PECO NuclOcr, FuOl & S rvicO3 Divicion PECO-COLR-L2RS L2R5 Cora Operating Limito Report Pcg3 24, Rev. 0 THW 2 ROD BLOCK MONITOR SETPOINTS Nominal Trip Allowable Value i Setpoint LTSP 117.1% 118.3% '

TSP .12.3% 113.5%

l HTSP 107.3% 108.5%

i DTSP 92% 89%  ;

l These se points are based on a MCPE limit of 1.31 (SLMCPR=1.12) and  ;

are consistent with a RBM filter time constant between 0.1 seconds  ;

and 0.55 seconds.

LTSP - 1:w trip setpoint ITSP - :ntermediate trip setpoint '

HTSP - High trip setpoint DTSP -  : wnscale trip setpoint i

'- PECO NuclOtr, Fu01 & ScrvicO3 Divicion P!CO-COLR-L2R5 L2R5 Caro Op3r; ting Limito Rep 3rt Pc"Jo 25, R0v. 0 TABLE 3 MAPLHGR SINGLE LOOP OPERATION (SLO) REDUCTION FACTOR SLO reduction factor = 0.79 for all Cycle 6 fuel types.

i i

I i

PECO NuclOnr, Fuol & S0rvicOO Divicion PECO-COLR-L2R5 L2R5 C ra Operating Limito Report Page 26, Rev. 0 TABLE 4 LINEAR HEAT GENERATION RATE LIMITS FUEL TYPE MAXIMUM VALUE GE6 13.4 kW/ft Gell 14.4 kW/ft GE13 14.4 kW/ft Gell (High Exposure LUA) 11.5 kW/ft NOTE: The LHGR is an exposure dependent value. Due to the proprietar/ nature of these values cnly -he maximum LHGR for each fuel type _s listed in Table 4. The LHGR data is listed

'in References 3 and 4 (GE proprietar/).

l- .-

PECO Nuc1COr, Fu3i & S rvicOc Divicion PECO-COLR-L2RS L2R5 Cara Operating Limits Report Paga 27, Rev. 0 TABLE 5 l

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

MINIMUM REOUTRED BYPASS VALVES TO MAINTAIN SYSTEM OPE? ABILITY lIumber Of valves = 7 l

l l

[

L

PECO Nuclocr, Fu3l & S rvic00 Divicien PECO-COLR-L2R5 l L2R5 Cora Operating Limito R port Pcg3 28, Rsv. O l.

(

TABLE 6 Recirculation Pump Motor-Generator (MG) Set Scoop Tabe Stops Mechanical 5 114%

Electrical 5 112%

l TABLE 7 Control Rod Block Instrumentation Reactor Coolant Syscem Recirculation Flow Upscale Trip l

Nominal Trip Setpoint 5113.4%

Allowable Value 5115.6%

l l

l l

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l l 1 l

i l

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