ML20199F749

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Rev 1 to PECO-COLR-P3C12, COLR for Pbaps,Unit 3,Reload 11, Cycle 12
ML20199F749
Person / Time
Site: Peach Bottom Constellation icon.png
Issue date: 11/03/1997
From: Carmody J, Mchale J, Payton D
PECO ENERGY CO., (FORMERLY PHILADELPHIA ELECTRIC
To:
Shared Package
ML20199F739 List:
References
PECO-COLR-P3C12, PECO-COLR-P3C12-R01, PECO-COLR-P3C12-R1, NUDOCS 9711250006
Download: ML20199F749 (21)
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Text

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' PEC0 Nucient Fuel and Services Division - PECO-COLR-P3C12

'j P3C12 Core Operating Umits Report Page 1 Ret'.1

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i CORE OPERATING LIMITS REFORT FOR PEACH BOTTOM ATOMIC POWER STATION UNIT 3 RELOAD 11, CYCLE 12 l REVISION 1

/-

Prepared By: O Date: ///3/'/7

  • S. f. Payton Engineer Nuclear Design & Materials Branch Reviewed By: e 2 /b b Date: ll!3 97

/I '

l h' ~ J. L. McHale Engineer L

Nuclear Design & Materia's Branch Approved By:

N Date: D 9)

) M. Carmody' l Manager l Nuclear Design & Materials Branch 4

I P PDR

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' ., PECd Nuc$w Fuel and Services Divisioti PECO COLR P3C12 l P3C12CoreOperaungUmtBRegat Page 2. Rev.1 -

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LIST OF EFFECTIVE PAGES

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' .' PEC Nuciear Fuel and Services Division PUCO COLR P3C12 1 P3C12 Core Operating Limits Report Page 3, Rev.1 INTRODUCTION AND

SUMMARY

This report provides the following cycle specific parameter limits for Peach Bottom Atomic Power Station Unit 3 Cycle 12 (Reload 11):

Maximum Average Planar Linear Heat Generation Rate (MAPLHGR)

  • ARTS MA DLHGR thermallimit multipliers Single Loop Operation (SLO) MAPLHGR multi, 'ers a Minimum Critical Power Ratio (MCPR)

+ ARTS MCPR thermallimit adjustments and multipliers

  • Single Loop Operation (SLO) MCPR adjustment
  • Rod Block Monitor (RBM) Analytical Limits, Allowable Values and MCPR Limits

. Linear Heat Generation Rate (LHGR)

Turbine Bypass Valve Parameters These values have been determined using NRC-approved methodology and are established such that all cpplicable limits of the plant safety analysis are met.

This report provides the means for calculating the Operating Limit MCPR and MAPLHGR thermal limits for the following conditions:

  • All points in the opvrating region of ine power / flow map including Maximum Extended Load Line Limit (MELLL) down to 81% of rated core flow during full power (3458 MWt) operation

+ Increased Core Flow (ICF), up to 110% of rated core flow End of Cycle Power Coastdown to a minimum power level of 40%

. Feedwater Heaters Out of Service (FWHOOS) to a maximum feedwater temperature reduction of 55 'F

+ Feedwater Temperature Reduction FWTR), to a maximum feedwater temperature reduction of 55 *F This report contains all thermallimit parameters related to the implementation of the ARTS Improvement Program and Maximum Extended Load Line Limit Analyses (ARTS / MELT.LA) for Peach Bottom Unit 3 Cycle 12. Revision 1 of this report incorporates cycle specific power dependent ARTS curves and a supplemental reference to Siemens Power Corporation (SPC) Lead Fuel Assembly (LFA) DESLIMS (R:ference (19)),

This report is submitted in accordance with Technical Specification 5.6.5 of Reference (1). Preparation of this report was performed in accordance with PECO Energy Fuel and Serwes Division Procedure

  • ' PEC0 Nucioar Fuel and Services Dwision PECO COLR P3C12 j P3C12 Core Operating Limits Report Page 4, Rev.1 FM 300," Reload Core Licensing".

MAELHGR LIMITS ThJ limiting MAPLHGR value for the most !imiting lattice (excluding natural uranium) of each fuel type as a function of average planar exposure is provided in Figures 1 through 4. The=e figures are used when h:nd calculations are required a specified in Reference (6). All MAPLHGR limits for each fuel type as a function of axial location and average planar exposure shall be 10ss than or equal to the applicable limit values for the respective fuel and lattice types to be in compliance with Technical Specification 3.2.1.

Th:se limit values are specifit iin References (3), (4), (5), (16) and the process computer databank. The Si: mens Fower Corporation gSPC) Lead Fuel Assemblies (LFAs) will be monitored to the modified GE9B-P8DWB32010GZ (Peach Bottom 2 Reload 8 bundle) MAPLHGR limits per References (10) and (16). The ARTS based MAPLHGR power-dependent multipliers (MAPFAC(P)) are provided in Figures 5 and 6. Figure 5 is valid for seven or more (of nine) Turbine Bypass Valves (TBVs) In Service. Figure 6 is salid for three or more (of nine) TBVs Out of Service (OOS). The flow dependent multipliers (MAPFAC(F)) are provided in Figures 7 and 8 as a function of the number of recirculation loops in operation only. The flow-dependent MAPLHGR multipliers were obtained from Reference (15). The power-dependent MAPLHGR multipliers were obtained from Reference (18).

MCffillMllS Tho Operating Limit MCPR (OLMCPR) for use in Technical Specification 3.2.2 for each fuel type is given in Table 1. These values are determined by the cycle specific fuel reload analyses in Reference (2). The OLMCPR is increased by 0.01 when operating in SLO (due to the safety limit MCPR increase).

Control rod scram tirne verification is required as per Technical Specification 3.1.4, " Control Rod Scram Times". Tau, a measure of scram time pertoimance to notch position 36 throughout the cycle, is d;termined based on the cumulative scram time test results. The calculation of Tau shall be performed in cccordance with site procedures.

Separate MCPR values are presented herein for the following domains:

Core Row s 100% of Rated, No FWHOOS/FWTR, TBVs in-Service Core Flow > 100% of Rated, up to 110% of Rated, With or Without FWHOOS/FWTR, TBVs In-Service

  • Core Flow s 100% of Rated, FWHOOS/FWTR, TBVs in Service Turbine Bypass Valves Out-of Service (TBVOOS), 3 or more out-of service, With All Other Domains The OLMCPR values are documented in Referenca (2) for the GE11 and GE13 fuel designs and R:ference (10) for the SPC LFAs.

The ARTS based power-dependent MCPR limits, OLMCPR(P), for use in Technical Specification 3.2.2 are provided in Figures 9 and 10. - Figure 9 is valid for seven or more TBVs In-Service. Figure 10 is valid for three or more TBVOOS. The flow-dependent MCPR limits, OLMCPR(F), are provided in Figure 11.

l The flow dependent OLMCPR curves were obtained from Reference (15). The power-dependent

' ' PECO Nuclear Fuel and Services Division PECO-COLR-P3C12 j P3C12 Core Operating Umits Report Page 5, Rev.1 l OLMCPR curves were obtained from Reference (18). ,

I OVERALL GOVERNING MCPR AND MAPLHGR LIMITS ARTS provides fct power and flow-dependent thermallimit adjustments and multipliers which allow for a more reliable administration of the MCPR and MAPLHGR thermallimits. At any given power / flow (P/F) st:ta, all four limits are to be determined: MAPFAC(P), MAPFAC(F), OLMCPR(P), and OLMCPR(F) from l Figures 5 through 11, inclusive [per References (7), (15) and (18)). The most limiting MCPR and the m:st limiting MAPLHGR [ maximum of OLMCPR(P) and OLMCPR(F) and minimum of MAPLHGR(P) and MAPLHGR(F)) for a given (P,F) condition will be the governing limits. The OLMCPR for each fuel type is d:termined by the cycle specific fuel reload analyses in Reference (2). Rated MAPLHGR values are a composite of results obtained from bundle spacific thermal mechanical and emergency core cooling system analyses. Supporting documentation for the AUS based limits is provided in Reference (0).

RQDJLOCK MONITOR SETPOINTS Th3 RBM power blased Analytical Limits Allowable Values and MCPR Limits for use in Technical Specification 3.3.2.1 are provided in Table 2 per References (7) and (8) with supporting documentation in R:ferences (2), (11) and (12).

LINEAR HEAT GENERATION RATES Th3 beginning of life (maximum) design LHGR limits for each fuel type for use in Technical Specification 3.2.3 are provided in Table 3. Conservative LHGR values as a function of fuel exposure are provided in l tha process computer data bank and Refererices (3) and (19). The bases for these LHGR values are documented in References (6) and (10).

STEAM BYPASS SYSTEM OPERABIL ,

Th3 operability requirements for the steam bypass system are governed by Technical Specification 3.7.6 and are further discussed in Reference (9). If the requirements cannot be met, the appropriate power / flow dependent limits for TBVOOS must be used (Table 1 with Figures 6 and 10). The minimum number of bypass valves to maintain system operability is seven as per References (2) and (9) and Table

'4. Table 4 also includes other Turbine Bypass Valve parameters.

BEFERENCES

1) ' Technical Specifications for Peach Bottom Atomic Power Station Unit 3", Docket No. 50-278, Appendix A to License No. OPR 56,
2) " Supplemental Reload Licensing Report for Peach Bottom Atomic F'ower Station Unit 3, Reload 11, Cycle 12", J1103093SRLR, Rev,0, August 1997.
3) . " Lattice Dependent MAPLHGR Report for Peach Bottom Atomic Power Station Una 3 Reload 11 Cycle 12', J1103093 MAPL, Revision 0, August 1997.

4).' Lattice Dependent MAPLHGR Report for Peach Bottom Atomic Power Station Unit 3 Reload 10 Cycle 11",24A5175AA, Revision 0, September 1995.

5)-

  • Lattice Dependent MAPLHGR Report for Peach Bottom Atomic Power Station Unit 3 Reload 0

~ ' PECd Nuclear Fuel and Services Division PECO-001.R:P3012 l P3C12 Core Operating Umits Repon Page 6. Rev.1 Cycle 10",23A7215AA. Revision 1, March,1994.

6)
  • General Electric Standard Application for Reactor Fuel", NEDE 24011-P A 13, August,1996; and U.S. Supplement. NEDE 24011 P-A 13 US, August 1996.
7) 'Maximuni Extended Load Line Limit and ARTS Improvement Program Analyses for Peach Bottom Atomic Power Station Unit 2 and 3", NEDC 32162P, Revision 2, March 1995.
8) Letter, G. V. Kumar to H. J. Ryan, " Justification for Reduction of Rod Block Monitor System Downscale Trip Setpoint For Peach Bottom Atomic Power Station", May 23,1994,
9) Letter, G. V. Kumar to G. C. Storey, *PBAPS Evaluation of Turbine Bypass Surveillance Requirementa", January 19,1995.
10) Siemens Power Corporation Report EMF 93115(P), " Peach Bottom Unit 3 9x9 A Lead Fuel Assembly Safety Analysis Report" July 7,1993,
11) PECO Energy Calc. PM 0875,"GE NSSS Setpoints Required to Support Power Rerate"
12) Letter, M. G. Wiwel to A. S. Hegedus and R. C. Stott,
  • Rod Block Monitor Downscale Settings for ITS", March 14,1995.
13) Letter, R. M. Butrovich to H. J. Diamond,
  • Peach Bottom Unit 3 Safety Limit MCPR", June 6,1997.
14) Letter, R. M. Butrovich to H. J. Diamond,
  • Peach Bottom Unit 3 Safety Limit MCPR", June 16,1997.
15) Letter, R. M. Butrovich to J. M. Carmody,
  • Appropriate Generic ARTS Curves for Peach Bottem 3 Cycle 12", August 12,1997.
16) Letter, M. R. Morris to G. R. Hull,
  • Peach Bottor" 3 Cycle 10 LFA Monitoring", September 27,1993.
17) Letter, J. L. Casillas to G. C. Storey, " Peach Bottom Atomic Power Station Unit 3 Cycle 12 ARTS Thermal Limits Analysis". October 31,1997.
18) ' Peach Bottom Atomic Power Station Unit 3 Cycle 12 Arts Thermal Limits Analyses",

J11 03093 ARTS, Rev. O, October 1997.

19) Design Verification Guide. " Peach Bottom 3 Cycle 12 LUA DESLIM Input File Changes",10/02/97

. PECb Nucieer Fuel and Services Division PECO-COLR P3012 1 P3C12 Core Operating Umits Report Page 7. Rev.1 FIGURE 1 MAXIMUM AVER AGE PLANAR LINEAR HEAT GENERATION RATE (MAPLHGR) VERSUS .

AVERAGE PLANAR EXPOSURE >

FUEL TYPE GE13 P9DTB40013GZ-100T 146 T n..

n.: / g THIS FIGURE IS REFERRED TO BY TECHNICAL $PECIFICATION 3 2.1

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Averno. n anar xxposur. (owa/st)

Avg Plan Avg Plan Avg Plan Exposure MAPLHGR Exposure MAPLHGR Exposure MAPLHGR (GWd/ST) (kW/ft) (GWd/ST) (hW/.fi) (GWd/ST) (kW/ft) 0.0 10.90 7,0 11.88 25.0 11.20 O.2 10.97 8.0 12.03 30.0 10.48 1.0 11.06 9.0 12.19 35.0 9.76 l

2.0 11.18 10.0 12.36 40.0 9.00 3.0 11.31 12.5 12.50 45.0 8.36 4.0 11,45 15.0 12.40 50.0 7.67 5.0 - 11.59 17.5 12.15 55.00 6.97 6.0 11.73 20.0 11.85 58.44 6.48

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

. PECd Nuclear Fuel and Services Division PECO COLR P3012 j ~P3C12 Core Operating Umits Report Page 8. Rev.1 FIGURE 2 .

MAXIMUM AVERAGE PLANAR LINEAR HEAT GENERATION RATE (MAPLHGR) VERSUS AVERAGE PLANAR EXPOSURE FUEL TYPE GE11 P9 HUB 40513GZ1 100T 146 T 18 8 THiS FIGURE is REFERRED TO BY l TECHNICAL SPECIFICATION 3 2.1 I I a...

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... ... se.. is.. n.. a.. .... n.. .... o.. so.e es.o ....

Average Planar Exposure (GWd/ST)

Avg Plan Avg Plan Avg Plan Exposure MAPLHGR Exposure MAPLHGR Exposure MAPLHGR (GWd/ST) (kWlft) (GWd'ST) (kW/ft) (GWd/ST) (hW/tt) 4 0.0 . 10.42 7.0 11.33 25.0 10.74 0.2 10.48 8.0 11.45 30.0 10.22 1.0 10.59 9.0 11.E7 35.0 9.62 2.0 10.73 10.0 11.63 40.0 8.97

' 3.0 10.84 12.5 11.65 45.0 8.31 4.0 10.96 15.0 11.56 50.0 7.62 5.0 11.08- 17.5 11.44 55.0 6.91 6.0 11.20 20.0 11.24 57.01 6.62

.' PECh Nuciear Fuel and Services Division PECO-COLR P3C12 (

1 P3C12 Core Operating 8 imits Report Page 9, Rev.1 FIGURE 3 MAXIMUM AVERAGE PLANAR LINEAR HEAT GENERATION RATE (MAPLHGR) VERSUS AVERAGE PLANAR EXPOSURE FUEL TYPE GE11 P9 HUB 36711GZ 100M 146 T n.~

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,e / \ THIS FlOURE IS REF ERRED TO BY TECHNICAL SPECIFICATION 3 2.1 I

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t o.. . .

le

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6.9 9.6 9. 10.8 15.0 30.0 31.w 10,0 16.0 40.0 45.9 ft.. 15.0 60.0 Average Planar Exposure (GWd/ST)

Avg Plan Avg Plan Avg Plan Exposure MAPLHGR Exposure MAPLHGR Exposure MAPLHGR (DWd'ST) (hWill) (GW.d1T) (kW/ft) (GWd/ST) (16Y1(1) 0.0 11.14 7.0 12.13 25.0 11.00 0.2 11,18 8.0 12.26 30.0 10.29 1.0 11.27 - 9.0 12.36 35.0 9.61 2.0 11.40 10.0 12.48 40.0 8.94 3.0 11.53 12.5 12.64 45.0 8.28 4.0 11.67 - 15.0 12.37 50.0 7.62 5.0 11.82 175 12.07 55.0 6.93 6.0 11.97- 20.0 11.73 57.64 6.56

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

9

'. PEC'd Nucib Fuel and Services Division PECO ColR P3C12

{ P3C12 Core Operating Limits Report Page 10. Rev.1 i

FIGURE 4 MAXIMUM AVERAGE PLANAR LINEAR HEAT GENRRATION RATE (MAPLHGR) VERSUS AVERAGE PLANAR EXPOSURE FUEL TYPE SPC 9x9 A (LFA) al.o a  ! I I

.e 7

/ '

THIS FIGURE IS REFERRED TO BY TECHNICAL SPECIFICATON 3 21 u.. -.

3...

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=

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6.0 00 4.0 10.0 11.0 38.6 St.D 10.0 31.6 40.0 45.9 10.0 15.4 Average Planar Exposure (GWd/ST)

Avg Plan Avg Plan Avg Plan Exposure MAPLHGR Exposure MAPLHGR Exposure MAPLHGR LOWd/ST) (kW/ft) (GWd/ST) (kW/ft) (GWd/ST) (kW/ft) 0.0 10.82 6.0 12.11 15.0 12.67 0.2 10.85 7.0 12.26 20.0 12.11 1.0 10.95- 8.0 12.42 25.0 10.74 2.0 11.13 9.0 12.56 35.0 9.53

. 3.0 11.34 10.0 12.71 45.0 0.29 4.0 11.58 12.5 -12.85 51.06 5.45 5.0 11.83 i

i

.

  • 4

. PECO Nuclear Fuel and Services Division PiCO-COLR.P3012 j P3C12 Core Operating Umits Report Page 11. Rev.1

~

FIGURE 5 POWER DEPENDENT MAPLHGR MULTIPLIER MAPFAC(P)

THIS FIGURE IS REFERRED TO BY TECHNICAL SPECIFICATION 3.2.1 VALID FOR 7 OR MORE TBVs IN SERVICE I

1.3 i

1.0 -....................................................................--g '

O.952 l

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< l l Ens . .

  • l l I ,. .o 0.788 l l g . .

O  :

y l MAPLHGR(P) . MAPFAC(P)

s 60% Flow l No Umsts Specifed i k

f 0.511 F r 25% s P c 30% : MAPFAC(P) 0 $11,0 012 * 'P - 30%)

For s 60% Core Flow y l MAPFAC(P) . 0 418 + 0 006 * (P 30%)

e Foc > 60% Core Flow

^ 0.413

]g . For 30% s P < 65% : MAPFAC(P) . 0 788 +0 00469 * (P - 30%)

B, g

0.388 l

%, For 65% s P <95% : MAPFAC(P) = 0 952+0 00159 ' (P 65%)

" For 95% s P : MAPFAC(P) .10

!  ! > 60% Flow l l l A  ;  ;

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o 10 ao 30 40 so so to ao so too Power (% Rated) i l

l. _ . - , , . . - . . . - , . - - . . . . ., . . - + ~ - - - - -,- - c

--n., -- -,

.' PECO Nuclear Fuel and Services Division PECO COLR P3C12

'l P3012 Core Operating Limits Report Page 12, Rev.1 l

FIGURE 6 POWER DEPENDENT MAPLHGR MULTIPLIER MAPFAC(P)

THIS FIGURE IS REFERRED TO BY TECHNICAL SPECIFICATION 3.2.1,3.4.1 AND 3.7.6 VALID FOR 3 OR MORE TBVs OOS 1.2 1.0 ~.......................................................................... i m

.n.

'O N l 0.901 ti.

m l l

g. 0.

l l

- l l fu 0.729 [  :

{

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q . IMAP6HGR(P). MAPFA0(P)* MAPLHGRstd N l a: s 60% Flow l MAPLHGRstd . Standard MAPLHGR Umsts o .

A

l l

For 25% > P : No Thermal Umsts Monitoring Requued No umits Specified y (  ;

0.511 For 25%5P c 30% : MAPFAC(P) = 0 511 + 0 012 * (P 30%)

for s 60% Core Flow e 0.451 .

MAPFAC(P) = 0 418 + 0 006 * (P 30%)

. l For > 60% Core Flow

]

$"* O.388 h For 30% s P c 65%

MAPFAC(P) . 0 729 + 0 00394 * (P 30%,

. . For 65% s P e 85%

$ l l MAPFAC(P) = 0 867 + 0 0017 * (P 65%)

g l l > 60% Flow For 85% s P :

g l l MAPFAC(P) . 0 901 + 0 0066 * (P 85%)

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

. ~

." PECd Noch Fuel and Services Division PECO-COLR P3C12

[ P3C12 Core Operating Umits Report Page 13 Rev.1 I

FIGURE 7 j FLOW DEPENDENT MAPLHGR MULTIPLIER MAPFAC(F)

THIS FIGURE IS REFERRED TO BY TECHNICAL SPECIFICATION 3.2.1 VALID FOR TWO LOOP REClRC FLOW 1.1 1- ,

0.9-  !

C l t  :

$0.8-  !

g  :

E l MAPLHGR(F) - M APFAC(F)

5 MAPFACf(F) = (At

  • We /100 + Bf), OR g - 1.0; whichever is lower lE 0.6 _ We = % Rated Core Flow 0.572 Af = 0.6682, Bf = 0.5055 0.5- j l

l l

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

~

' e' PECN'Mudar Fuel and Services Olvision PECO COLR.P3C12 )

l* P3C12 Core Operating Limits Report Page 14, Rev.1 FIGURE 8 FLOW DEPENDENT MAPLHGR MULTIPLIER MAPFAC(F)

THIS FIGURE IS REFERRED TO BY TECHNICAL SPECIFICATION 3.2.1 AND 3.4.1 VALID FOR SINGLE LOOP RECIRC FLOW l

l 1.1 l

1-0.0- ,,

E  !

W i it4 l I 0.8 - l I

E ,i m

j MAPLHGR(F) - MAPFAC(F)

'eC.7 - MAPLHGRstd = Standard MAPLHGR Limits fg MAPFACf(F) = (Af

  • We /100 + Bf), OR

= 0.9; whichever is lower lE 0.6- We = % Rated Core Flow 0.572 Af = 0.6682. Bf = 0.5055 l

0.5- ,

l

=

l l

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

!) TABLE 1 .  ;

OPERATING Lill1!T MINIMUM CRITICAL POWER RATIO (OLMCPR ) -

Use in conjunction with Figures 9,10, and 11 .

GO I Add 0.01 to the'OLMCPR when in Single Lcop Operation

This Table is referred to by Technical Specification 3.2.2,3.4.1 and 3.7.6  ;

. aL i i'

CCRE FLOW s100% OF RATED > 100% OF RATED s 100% OF RATED ANY k!

g NN NO YES OR NO YES YES OR NO j TBVs IN IN IN OUT

_ _ _ _ _ _ _ _ . . . _. __ _ _ _-SER VIC E_ ____ _.____ ____

_ _-SERVICE ___ _______

__ _ _ ___-SERVICE _.__________ ___ _._-OF SERVICE __._____ _ y ,

Opt. B Opt. A Opt. B Opt. A - Opt. B Opt. A Opt. B Opt. A { i i-

< Reload 10 - - l . MOC 135 -138 135 1.39 135 138 1.40 1.45 - r l GE11 Only j .- EOC 1.37 1.45 1.38 1.46 1.38 1.46 1.45 1.53 Reload S GE11 l MOC 1.33 1.38 134' 1.39 133 1.38 1.40 1.45 and GE13 EOC- 137 1.45 138 1.46 1.38 1.46 1.45 1.53

l
i. -SPC f MOC 1.39 1.42 1.39 1.43 1.39 1.42 1.44 1.49 i EOC 1.41 1.49 1.42- 1.50 1.42 1.50 1.49 1.58

! I NOTES: 1) Opt. B: Tau =0.0  ;

i

2) Opt. A: Tau =1.0
3) When Tau does not equal 0.0 or 1.0, use linear interpolation to two significant figures (e.g.,135).

! 4) MOC: Cycle exposure from BOC to EOR-2000 mwd /ST.

! 5) EOC: Cycle exposure from EOR-2000 mwd /ST to EOC

6) FWHOOS: Feedwater Hester Out-of-Service, maximum 55 'F r 7) FWTR: Feedwater Temperature Reduction, maximum 55 'F - j l

l

8) TBVOOS: Turbine Bypass Valves Out-of-Service (3 or more TBV's 006)

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' ' PECh Nuclear Fuel and Services Olvision PECO COLR P3012 l l P3C12 Core Operating Limits Report Page 16, Rev.1 FIGilRE 9 POWER DEPENDENT MCPR LIMIT ADJUSTMA.NTS AND MULTIPLIERS THIS FIGURE IS REFERRED TO BY TECHNICAL SPECIFICATION 3.2.2 VALID FOR 7 OR MORE TBVs IN SERVICE J.4-li.25 3,3 ,

OPERATING LIMIT MCPR(P) . Kp ' OLMCPR{100)

Y '

FOR P<25% : NO THERMAL LIMIT MONITORING REQUIRED

~ li*) LIMITS SPECIFIED 9:. s . 0 - > 60% Flow k

U f g'gg FOP 25% P c Pbypass :(Pbypass . 30%)

e . OLMCPR(P) . Kbf p

  • fJ SPE * (30% P) 3 2.. . 2.78 : i k6xa - 2 2$ ron ico* coae r'o*

O . Kbyp . 2 91 FOR > 60% CORE FLOW

,  : SLOPE . 0104 FOR 5 60% CORE FLOW

: SLOPE . 0 068 FOR > 60% CORE FLOW
3. 6 - . .
  • FOR 30% s P < 65% : Kp . I 13 + 0 00386 * (65% P) 3,,. /y: .

FOR 66% s P c 85% : Kp 1056 0 00050 ' (B!% -P) f FOR 85% s f Kp .100 + 0 00180 * (100% P) s GO% Flow

! ABSOLUTE  :  :

l l l 2.0 -

so S MULTIPLIER  !  !

1. e - ,

3  :  :

, a  :  :

t 2. s .  :  :

, E, . .

a  :  :

s.  :  :

=1s. . .

$ l l1.265 C e t.-

f! 1.130 i

y  :

i 1.066 - _

1.056 g 3,,

1027^ _,

0 10. 30 30 40 50 60 70 to 90 100

, Power (% Rated)

l

.' PECh Nuclear Fuel and Services Division PECO-COLR P3C12 l #3C12 Core Operating Limits Report Page 17. Rev.1 FIGURE 10 POWER DEPENDENT MCPR LIMIT ADJUSTMENTS AND MULTIPLIERS THIS FIGURE IS REFERRED TO BY TECHNICAL SPECIFICATION 3.2.2 AND 3.7.6 i l

VALID FOR 3 OR MORE TBVs OOS 1 l

3,3 3.25 3 OPERAT!NG UMIT MCPR(P) . Kp

  • OLMCPR(100) 3.o - FOR P<25% : NO THERMAL UMIT MONITORING REOL,.AFD l

NO LIMITS SPECIFIED

> 60% Flow  ! 2.91

- l l FOR 25% s P < Ptr/ pass : (Pbypass . 30%)

ae- O.MCPR(P) = Kbyp + SLOPE ' (30% P) 2*M Kbyp . 2 26 FOR s 60% CORE FLOW g l g . . Kbyp . 2 91 FOR > 60% CORE FLOW 5 2. s <

l l SLOPE . 0104 FOR s 60% CORE FLOW O l l SLOPE . 0 068 FOR > 60% CORE FLOW l l

  • FOR 30% s P < 65% : Kp .1.13 + 0 00514 * (65% . P) 2,4 -

FOR 65% s P < 85% : Kp . t 056 + 0 00175 * (85% . P)

Y, ( FOR 85% s P : Kp .100 + 0 00280 * (100% . P) a.a s 60% Flow . .

l l ABSOLUTE j j 3.o , ,

MULTIPLIER l l

, # l l g 2.s  ;

d' l

l 0 l g i. -  ;  ;

F l l 3 l l 3

1.4 i i

. 1.310 i  ;

e l l

1. 2 -  ; l 1.130 1 056

] l l 1.09r i 1042-g 3,, '

o to ao so ao so so to so so loo Power (% Rated)

. i

.' PEdd Nutdear Fuel end Services Olvision PECO COLR #3C12

( P3C12 Core Operating Limits Report Page 18. Rev.1 l

FIGURE 11 FLOW DEPENDENT MCPR LIMITS OLMCPR(F)

THIS FIGURE IS REFERRED TO BY TECHNICAL SPECIFICATION 3.2.2 2-1.9-For Wc (% Rated Core Flow) < 40%

8 3,jg2 OLMCPR(F) = (Af

  • Wc/100+Bf) * [1+ 0.0032 * (40 -Wc))

1.7 -

For We (% Rated Core Flow) a 40%

OLMCPR(F) = (Af

  • We/100+Bf). OR 1.25; whichever is greater g 1.6 -

g 1.569 Q- .

l Af = - 0.5526 * (1.11/1.07) = - 0.5733 0 1.5-  ! Bf = 1.6311 * (1.11/1.07) = 1.6921 l 1.463 l l l l 1.4 l l l l l l l l 1.3 l l l l 1.2:i l l .

l l l 1.2 - l

{ { ,

l l l l l l l l l 1,1  ?  ! ' ' ' ' ' '

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

~ , - , , , ,v-r,- , - - , -,-----ev- , - --- ~,- -

. .' PECb Nucloor Fuel ord Cervices olvision PECO-COLR-P3C12 j P3C12 Core Operating Limits Report Page 19, Rev.1 TABLE 2 ROD BLOCK MONITOR ANALYTICAL LIMITS, ALLOWABLE VALUES, AND MCPR LIMITS THIS TABLE IS REFERRED TO BY TECHNICAL SPECIFICATION 3.3.2.1 FUNCTION ANALYTICAL ALLOWABLE MCPR LIMlf" VALUE"' LIMIT Low Power Range - Uoscale s 120.0 % s 118.4 % < 1.70

  • Intermediate Power Range Upscale s 115.2% s 113.6 % < 1.70
  • High Power Range Upscale s 110.2 % s 108.6 % < 1.70 *

< 1.40

  • Inop N/A N/A < 1.70 *

< 1.40

  • Downscale 2 1.0% 2 2.5% < 1.70 *

< 1.40

  • Bypass Time Delay"' --- ---- ----

-(1) These Trip Level Settings (with RBM filter) are based on the rateo RWE MCPR limit which is less than or equal to the minimum cycle OLMCPR (see COLR references 1,7 and 11).

(2) This is the MCPR limit (given THERMAL POWER 2 28.3% and < 90% RTP) below which the RBM is required to be OPERABLE (see COLR reference 7 and TS Table 3.3.2.1 1),

(3) This is the MCPR limit (given THERMAL POWER 2 90% RTP) below which the RBM is required to be OPERABLE (see COLR reference 7 and TS Table 3.3.2.1-1).

(4) This time delay option is _ currently not in use at Peach Bottom Unit 3 (see COLR reference 7).

  • .' PEdhNuctear Fuel and Services Division PECO-COLR-P3C12

[ P3C12 Core Operating Limits Report Page 20. Rev.1 TABLE 3 DESIGN LINEAR HEAT GENERATION RATE (LHGR ) LIMITS' j FUEL TYPE LHGR LIMIT GE13 14.4 kW/ft GE11 14.4 kW/ft j SPC 9x9 A(LFA) 14.4 kW/ft i

i 4

' The LHGR limits provided above are the beginning of tafe (maximum) values. LHGR limits as a function of fuel exposure are provided in the process computer data bank and COLR References (3) and (19).

~

e. PED Nuclear Fuel and Services Division PECO-COLR P3C12 j P3C12 Core Operating Limits Report Page 21. Rev.1 TABLE 4 i

TURBINE BYPASS VALVE PARAMETERS TURBINE BYPASS SYSTEM RESPONSE TIME Maximum delay time before start of bypass valve opening following generation of the turbire bypass 0.10 sec.

valve flow signal Maximum time after generation of a turbine bypass valve flow signel for bypass valve position to reach 0.30 sec.

80% of full flow (includes the above delay time)

Minimum required number of bypass valvet. to maintain system operability 7 l eMdWotes.Sc12ft. doe

. . - - . _ . . . - - . . - _ .

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