ML20198C675

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Rev 3 to COLR for PBAPS Unit 3,Reload 11,Cycle 12
ML20198C675
Person / Time
Site: Peach Bottom Constellation icon.png
Issue date: 11/05/1998
From: Carmody J, Payton S, Robert Wolfgang
PECO ENERGY CO., (FORMERLY PHILADELPHIA ELECTRIC
To:
Shared Package
ML20198C671 List:
References
PECO-COLR-P3C12, PECO-COLR-P3C12-R03, PECO-COLR-P3C12-R3, NUDOCS 9812220135
Download: ML20198C675 (21)
v • d • e


Text

. _ . . _ _ _, _.. . . _ - . . _ _ . . . - . _ _.

PECO COUWJC12

'.', l P3C12 PECONucieer Core Operaung Fueland M Report Wm Page 1, Rev.3 CORE OPERATING LIMITS REPORT FOR PEACH BOTTOM ATOMIC POWER STATION UNIT 3 RELOAD 11, CYCLE 12 l- REVISION 3 Prepared By: . <

h/ Date: Il!3f 78 S. #. Payton Engineer Nuclear Design & Materials Branch  ;

i Reviewed By: & //d 7 Date: //M/#

'R. J. W6tkjang Engineer Nuclear Design & Materials Branch ,

~

Approved By: 't / Date: I'/deJ

  1. J. M. Carrft6by l Manager -

Nucleer Design & Materials Branch l

I i 9812220135 ADOCK O 981214 28 9 pDR L

l

e ,

f PECO Nuclear Fuel and Services DMalon PECOCOUW3C12

, ] ' P3C12 Core Operating Lhnits Report Page 2, Rev.3 LIST OF EFFECTIVE PAGES Page(s) Revision "

l 1 - 21 3

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

PECO Nuclear Puel and Services Division PECOCOLR.P3C12

] P3C12 Core Operating Limits Report Page 3, Rev.3 INIBQQUCIlQtiAND_StaGIABY 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 MAPLHGR thermallimit multipliers Single Loop Operation (SLO) MAPLHGR multipliers Minimum Critical Power Ratio (MCPR)

ARTS MCPR thermal limit 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 xse values have been determined using NRC-approved methodology and are established such that all

,; plicable limits of the plant safety analysis are met. '

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

All points in the operating region of the power / flow map including Maximum Extended Load Line l

Limit (MELLL) down to 81% of rated core flow during full power (3458 MWt) operation 4

  • Increased Core Flow (ICF), up to 110% of rated core flow l 1

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 /MELLLA) for Peach Bottom Unit 3 Cycle 12. ,

This report is submitted in accordance with Technical Specification 5.6.5 of Reference (1). Preparation of l

is report was performed in accordance with PECO Energy Fuel and Services Division Procedure FM-300," Reload Core Licensing".

I

I PECD Nuclear Fuel and Senr6ces Division PECO COLR-P3C12

. , l P3C12 Core Operating Limits Report Page 4, Rev. 3 APLHGR LIMITS The bounding MAPLHGR limits (kW/ft) for each fuel type are provided in Figures 1 through 4. The bounding MAPLHGR limits are the lowest kW/ft limits of the fuel lattices (excluding natural uranium) which comprise a given fuel type as a function of average planar exposure. The MAPLHGR figures l are used when hand calculations are required as specified in Reference (6). All MAPLHGR values for '

each fuel type as a function of axiallocation and average planar exposure shall be less than or equal to l tho applicable MAPLHGR limits for the respective fuel and lattice types to be in compliance with '

Technical Specification 3.2.1. These MAPLHGR limits are specified in References (3), (4), (5), (16) and  :

the process computer databank. The SPC LFAs will be monitored to the modified GE98-P8DWB320- l 10GZ (Peach Bottom 2 Reload 8 bundle) MAPLHGR limits per References (10) and (16). The ARTS- I 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 valid 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 operacion only. The flow-l d: pendent MAPLHGR multipliers were obtained from References (15) and (21). The power-dependent MAPLHGR multipliers were cttained from Reference (18).

MCPR LIMITS l

The Operating Limit MCPR (OLMCPR) for use in Technical Specification 3.2.2 for each fuel type is given ,

N Table 1. These values are determined by the cycle-specific fuel reload analyses in Reference (2). The LMCPR is increased by 0.01 when operating in SLO (due to the safety limit MCPR increase).

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

Separate MCPR values are presented herein for the following domains:

. Core Flow 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 Reference (2) for the GE11 and GE13 fuel designs and References (10) and (20) 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 r three or more TBVOOS. The flow-dependent MCPR limits, OLMCPR(F), are provided in Figure 11.

l The flow-dependent OLMCPR curve was obtained from Reference (21). The power-dependent OLMCPR

i PECO COLR-P3C12 l

' . .l'P3C12PECO Nucieer Core Opersdng Umits Report fuel and Services Division Pege 5, Rev.3 curves were obtained from Reference (18).

OVERALL GOVERNING MCPR AND MAPLHGR LIMITS 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. At any given power / flow (P/F) state, 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), (18) and (21)]. The most limiting MCPR and the most 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 ilmits. 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-specific thermal-mechanical and emergency core cooling system analyses. Supporting documentation for the ARTS-based limits is provided in Reference (6).

ROD BLOCK MONITOR SETPOINTS The RBM power-biased 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 References (2), (11) and (12).

LINEAR HEAT GENERATION RATES The beginning of life (maximum) design LHGR limits for each fuel type for use in Technical Specification

.2.3 are provided in Table 3. Conservative LHGR values as a function of fuel exposure are provided in e process computer data bank and References (3) and (19). The bases for these LHGR values are documented in References (6) and (10).

STEAM BYPASS SYSTEM OPERABILITY Tha 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 systern operability is seven as per References (2) and (9) and Table

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

REFERENCES

1) " Technical Specifications for Peach Bottom Atomic Power Station Unit 3", Docket No. 50-278, Appendix A to License No. DPR-56. I
2) " Supplemental Reload Licensing Report for Peach Bottom Atomic Power Station Unit 3, Reload 11, Cycle 12", J11-03093SRLR, Rev. O, August 1997.
3) " Lattice Dependent MAPLHGR Report for Peach Bottom Atomic Power Station Unit 3 Reload 11 Cycle 12", J11-03093 MAPL, Revision 0, August 1997. j
4) " Lattice Dependent MAPLHGR Report for Peach Bottom Atomic Power Station Unit 3 Reload 10 Cycle 11",24A5175AA, Revision 0, September 1995.

1

PECO Nuclear Fuel and Senrices Division PECO COLR-P3C12

"( P3C12 Core Operating umits Report Page 6, Rev. 3

5) " Lattice Dependent MAPLHGR Report for Peach Bottom Atomic Power Station Unit 3 Reload 9

. 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) ' Maximum Extended Load Line Limit and ARTS Improve' ment 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, "Justificatinn 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 Requirements", January 19,1995.
10) Siemens Power Corporation Report EMF-93-115(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.
1) 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 Bottom 3 Cycle 12", August 12,1997.
16) Letter, M. R. Morris to G. R. Hull, " Peach Bottom 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
20) Letter, D. Garber to A. Olson. " Transmittal of Condition Report 6508*, February 26,1998.
21) " ARTS Flow -Dependent Limits with TBVOOS for Peach Bottom Atomic Power Station and Limerick Generating Station", NEDC-32847P, June 1998.

PECO COLR-P3C12

' ' . ), Pl!C6 P3C12 Nuclear Core Operating UmitsFuel Report and Services DMelon Page 7 Rev.3 I FIGURE 1 MAXIMUM AVERAGE PLANAR LINEAR HEAT GENERATION RATE (MAPLHGR) VERSUS AVERAGE PLANAR EXPOSURE I

FUEL TYPE GE13-P9DTB400-13GZ-100T-146-T

- - . l 25.0  !

~

g THIS FIGURE IS REFERRED TO BY 12.o ,/ TECHNICAL SPECIFICATION 3.2.1

. ,,., / \

2..e \h

.0 i ..e N\ I

\  !

7.0 N

0.0 5.0 0.0 5.0 10.0 15.0 20.0 25.0 20.0 15.0 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 10.90 7.0 11.88 25.0 11.20 0.2 10.97 8.0 12.03 30.0 10.48 1.0 11.06 9.0 12.19- 35.0 9.76 2.0 11.18 10.0 12.36 40.0 9.06 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

' ,, { P3C12 Core Operat!ng Umits Report
Page 8, Rev.3 FIGURE 2 MAXIMUM AVERAGE PLANAR LINEAR HEAT GENERATION RATE (MAPLHGR) VERSUS AVERAGE PLANAR EXPOSURE l

FUEL TYPE GE11-P9 HUB 405-13GZ1-100T-146-T l

14.0 -

i 13.0 THIS FIGURE IS REFERRED TO BY TECHNICAL SPECIFICATION 3.2.1 j

12.0 i

25 '

. x I N

l CE

\

g10.0

'* \

..e x t

7.0 x

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 10.42 7.0 11.33 25.0 10.74 i

0.2 10.48 8.0 11.45 30.0 10.22 i 1.0 10.59 9.0 11.57 35.0 9.62 l

2.0 10.73 10.0 11.69 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 1

i

PECO COLR-P3C12

., ] P3C12

  1. EDO Core hbclear~

Operating Umits Fuel Report and Services Division Page 9, Rev.3 FIGURE 3 MAXIMUM AVERAGE PLANAR LINEAR HEAT GENERATION RATE (MAPLHGR) VERSUS AVERAGE PLANAR EXPOSURE FUEL TYPE GE11-P9 HUB 367-11GZ-100M-146-T u.0 l-

/

/ THIS FIGURE IS REFERRED TO BY 3,,, TECHNICAL SPECIFICATION 3 2.1 11.0 5

s 10.0 \

8 50.0 \,

0.0 - \

\

I 7.0 4.0 0.0 9.3 10.0 15.0 20.0 25.0 30.0 35.0 50.0 55.0 40.0 45.0 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) l 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 l 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 17.5 12.07 55.0 6.93 6.0 11.97 20.0 11.73 57.64 6.56

e

,* <sy P., ,av-s%CAGw iJ: .. . G 4 P : No Thermal Umits Morwtoring Required s 60% Flow a No Um ts Specified 0.511 F r 25% s P < 3 % : MAPFAC(P) = 0.511 + 0.012 * (P - 30%)

For s 60% Cue Flow y l MAPFAC(P) = 0.418 + 0.006 * (P 30%)

e

  • For > 60% Core Flow e 0.451* 0.418 g

2, , ,/

For 30% s P < 65% : MAPFAC(P) = 0.788+0.00469 * (P 30%)

y 0.388F %

  • For 65% s P <95% : MAPFAC(P) = 0 952+0.00159 * (P - 65%)

e  !  ! > 60% Flow For 95% s P : MAPFAC(P) 1.0

) . .

o '

As l l . .

.2 j j j j l l l l l l l l -

. l l l l l l l l l l l l l l o.O l O 10 20 30 40 50 60 70 80 90 100 Power (% Rated)

l PECO-COLR-P3C12

".. ..P3C12

] P'EC'O Core OperatingNuclear Limits Report Fuel and Services Division Page 12, Rev.3 I

FIGURE 6 1

POWER DEPENDENT MAPLHGR MULTIPLIER MAPFAC(P) i THIS FIGURE IS REFERRED TO BY TECHNICAL SPECIFICATION 3.2.1,3.4.1 AND 3.7.6 1

VALID FOR 3 OR MORE TBVs OOS 1.2 I

l 1.0 .......................................................................... p I n

a w

0 0.867

< 0.901 h

pe . l g l l

4 0.e - . .  ;

$ b o 0.729 ' - '

u ' '

. l E l IMAPLHGR(P)- MAPFAC(P)

  • MAPLHGRstd g s 60% Flow  ! lMAPLHGastd - Standard NiAPLHGR Umits o . ,

0*'~

j For 25% > P ; No Thermal Umits Morutoring Required A {

. No Umits Spe;&d M ( ,

0.511 For 25% s P < 30% : MAPFAC(P) = 0.511 + 0.012 * (P - 30%)

For s 60% Core Flow b 0.451  ! ,

MAPFAC(P) = 0.418 + 0 006 * (P 30%)

O

'c .

0.418 For s 60% Core Flow m \

c0 O,388 g,g y '  ;

iFo 30*/.5P < 65%

MAPFAC(P) = 0.729 + 0.00394 * (P - 30%)

. For 65% s P < 85%

l

.\

l \

MAPFAC(P) = 0.667 + 0 0017 * (P . 65%)

3 l* > 60% Flowi orF 85% s P :

j MAPFAC(P) - 0.901 + 0.0066 * (P 85%)

0. 2 -  !

l l l l l l l l  :. l l l l l l l l l

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

_ . _ . . ~ .__. .. . _ . . _ _ _ __ _ _ _ . .._ __ _ _ _ _

l' l - ,

i

' . . .. P'E60* Nuclear Fuel and Services Division PECO-COLR-P3C12 l l P3C12 Core Operating Units Report Page 13. Rev. 3 FIGURE 7 FLOW DEPENDENT MAPLHGR MULTIPLIER MAPFAC(F) i THIS FIGURE IS REFERRED TO BY TECHNICAL SPECIFICATION 3.2.1 VALID FOR TWO LOOP RECIRC FLOW 1.1 1.00 0.973

. l l l l l l l 0.9 -- l l c l l

[f l

It l l l 4 *

  • 2 0.8 --

l l u . .

o l l M  : l

u. . .

B 0.706 MAPLHGR(F) = MAPFAC(F)

@ l For Two Loop Operation, >70% We d

  • MAPFAC(F) =_ (0.0268 *(We - 70) /10 + 0.9732}, OR j - 1.0; whichever is lower 0.6 -- ~l For Two Loop Operation, s 70% We 0.572 i  ! MAPFAC(F) = {0.6682 *(Wc/100) + 0.5055) l l

We = % Rated Core Flow 0.5 --

{ { {

l l l l l l l

  • l l l l 0.4
! l l l  !  ! l l l

l 10 20 30 40 50 60 70 80 90 100 110 p.

Core Flow (% Rated) l

' . . P'EC0' Nuclear Fuel CM Services Division PEC(MOLR P3012

'l - P3C12 Core Operating Umits Report Page 14, Rev.3 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 1.1 1--

0.9-- -

h

^

It 2 0.8 --  :

i  :

li u.

i 3 '

MAPLHGR(F) - MAPFAC(F)

5 3 MAPFACf(F) = (Af

  • We /100 + Bf), OR g = 0.9; whicheve-is lower 2

0.6 _ We = % Rated Core Flow 0.572 Af = 0.6682, ' Bf = 0.5055 l

0.5 --

0.4 l l l l l 3h.'u l l l 10 20 30 40 50 60 70 ' 80 90 100 110 Core Flow (% Rated) ,

~

TAbst1 ,

OPERATING LIMIT MINIMUM CRITICAL POWER RATIO (OLMCPR )

- $g a Use in conjunction with Figures 9,10, and 11 i30 Add 0.01 to the OLMCPR when in Single Loop Operation g

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

s 100% OF RATED > 100% OF RATED s100% OF RATED ANY FLOW [

N 8#

NO YES OR NO YES YES OR NO

" IN

- _ _ _ _ _ _ _ _ _ . ___ _;SERqCE

, , _ _ _ _ _ _ ____{N-SERyICE SERVIC

_____y_,_____p____ OUT

__,___g[gypy__E C _,

Opt. B Opt. A Opt. B Opt. A Opt. B Opt. A Opt. B . Opt. A g Reload 10 MOC 1.35 .1.38 .1.35 1.39 1.35 1.38 l 1.40 1.45 GE11 Only EOC 1.37

! 1.45 1.38 1.46 1.38 1.46 1.45 1.53 Reload 9 GE11 f MOC 1.33 1.38 1.34 1.39 1.33 1.38 1.40 1.45 and GE13 EOC 1.37 1.45 l 1.38 1.46 1.38 1.46 1.45 1.53 SPC f:MOC 1.50 '1.S3 1.50 1.54 1.50 1.53 1.56 1.61 l EOC 1.52 1.61 1.53 1.62 1.53 1.62 i 1.61 1.71 NOTES: 1) Opt. B: Tau =0.0

2) Opt. A: Tau =1.0
3) When Tau does not equal 0.0 cr 1.0, use linear interpolation to two significant figures (e.g.,1.35).
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 Heater Out-of-Service, maximum 55 *F
7) FWTR: Feedwater Temperature Reduction, maximum 55 *F
8) TBVOOS: Turbine Bypass Valves Out-of-Service (3 or more TSV's OOS) g d
. . . . :, - o .

\

PECO NuclearYuel and Services DMslon l ., l P3612 Core Operaung Nts Report PECO COLR-P3012 Page 16, Rev.3 FIGURE 9 POWER DEPENDENT MCPR LIMIT ADJUSTMENTS AND MULTIPLIERS THIS FIGURE IS REFERRED TO BY TECHNICAL SPECIFICATION 3.2.2 i

VALID FOR 7 OR MORE TBVs IN-SERVICE 3.s-i 3.25 1

3. 2 - , OPERATING UMIT MCPR(P)- Kp
  • OLMCPR(100) J FOR Pc25% : NO THERMAL LIMIT MONITORING REQUIRED l NO UMITS SPECIFIED C_- 3. 0 - > 60% FMw .

m

  • ca.  !

2.91 FOR 25% s P < Pbypase :(Pbypass - 30%)

g  ; *

, OLMCPR(P) - Kbyp + SLOPE * (30% - P) a 2.s- 2.78 ' l Kbyp = 2.26 FOR s60% CORE FLOW O .

Kbyp - 2.91 FOR > 60% CORE FLOW

. l SLOPE = 0.104 FOR s 60% CORE FLOW

2. 6 -

l l SLOPE - 0 068 FOR > 60% CORE FLOW FOR 30% s P < 65% : Kp - 1.13 + 0 00386 * (65% . P) 2.4 p *l I FOR 65% s P < 85% : Kp - 1.056 + 0.00050 * (85% -P) )

s 60% FIOw l FOR 85% s P : Kp - 1.00 + 0.00180 * (100% . P) ,

2.26 l 2.2 - l l '

ABSOLUTE  !  ! l 2.0

$ MULTIPLIER  !  ! I 93 l l

o. i.e- l u l l ,

2 *

  • 1 E I E
1. 6 - l l l

.5  !  !

3i. l l g 1. 4 -

l l 1

2 l l 1.265 m- -

i Q. l l

o 2. 2 - .

i 1.130 l 3 1.056 l l 1.066 _ -

5 g ,0 4.

e

  • 1.027 '  ;

1 0 10 20 30 40 50 60 70 80 90 100 Power (96 Rated) l l

  • ' . . . PEDO. Nuclear' Fuel and Services Division PECO COLR-P3C12 l l P3C12 Core Operating Limits Report Page17 Rev.3 t

FIGURE 10 POWER DEPENDENT MCPR LIMIT ADJUSTMENTS AND MULTIPLIERS THIS FIGURE IS REFERRED TO BY TECHNICAL SPECIFICATION 3.2.2 AND 3.7.6 VALID FOR 3 OR MORE TBVs OOS t

3.2 - 3.25

! l l OPERATING UMIT MCPR(P)- Kp

  • OLMCPR(100) l 3.0  ; FOR P<25% : NO THERMAL UMIT MONITORING REQUIRED

=

NO UMITS SPECIFIED i

> 60% Flow l 2.91 '

l l FOR 25% s P < Pbypass :(Pbypass - 30%)

f g 2.8 - 2.78 { OLMCPR(P) - Kbyp + SLOPE * (30%-P) '

g ,  ; Kbyp - 2.26 FOR s 60% CORE FLOW Q  ;  ; Kbyp - 2.91 FOR > 60% CORE FLOW

  • SLOPE - 0.104 FOR s 60% CORE FLOW .-

j O 2.s - SLOPE - 0.068 FOR > 60% CORE FLOW l l l

l l FOR 30% s P < 66% : Kp - 1.13 + 0.00614 * (65% - P) 2.4- '

l l FOR 65% s P < 85% : Kp - 1.056 + 0.00175 * (85% . P) l g'g FOR 85% s P : Kp - 1.00 + 0.00280 * (100% - P) l 2.2 s 60% Flow l l I l l ABSOLUTE l l I 2.0 l MULTIPLIER -  !  ! '

g 1.s-l l n  ;  ;

e' l

l

! S l l l g, 1. s -  ;  ;

26.- l l 1 l 5 l l l

= . . .

Q. 1. 4 - *

  • I E l 1.310 s .

I E -

  • l' cc l l

$ 1.2 - l 1.130 2 l l 1.056 l l 1.091 - -

E.- . .

1.04 & ,

p 1.0 0 10 20 30 40 50 60 70 80 90 100 Power (% Rated) i

PECO COLR P3C12 I

' . .)P3C12 PEC'O NuclearFuel Core Operating Lhnits Report and Services Division Page 18, Rev. 3 FIGURE 11 l FLOW DEPENDENT MCPR LIMITS OLMCPR(F)

THIS FIGURE IS REFERRED TO BY TECHNICAL SPECIFICATION 3.2.2 VALID FOR ALL CONDITIONS  !

l 2

1.9 --

l i

1.808 i For Two Loop Operation, SLMCPRi 1.12,2.40% We MCPR(F)- {-0.5784 * (Wc/100) + 1.7073) OR- i 1.25; whichever is greater l

1.7 --

For Two Loop Operation. SLMCPR s 1.12 < 40% Wc MCPR(F)= {-0.5784 * (Wc/100) + 1.7073)

  • l

{1 + 0.0032 * (40 - Wc)) l g 1.6 -- c = */. raw Core Row

  • 1.583 g .
a.  :

O 1.5 -- l 1.476 1.4 -- l {

l-l l l l 1.3 --  :

1.25 l-  : ..
: I 1.2 --  ; +- l l l 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)

j

~

! . . 'PECO Nucient Fuel and Services Division PECO-COLR-P3C12 l l P3C12 Core Operating Umits Report Page 19, Rev.3 I i l

TABLE 2 l l .

i ROD BLOCK MONITOR ANALYTICAL LIMITS, ALLOWABLE VALUES, AND MCPR LIMITS  !

THIS TABLE IS REFERRED TO BY TECHNICAL SPECIFICATION 3.3.2.1 l FUNCTION ANALYTICAL ALLOWABLE MCPR LIMIT" VALUE'" LIMIT I Low Power Range - Upscale 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

  • I Inop N/A N/A < 1.70 *  !

< 1.40

Downscale 2 1.0% 2 2.5% < 1.70

  • l < 1.40
  • l Bypass Time Delay * --- --- ----

i . -

(1) These Trip Level Settings (with RBM filter) are based on the rated 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).

l

l l .,l. P3C12 Pff0Nucleaf Core Operating FuelandServicesDMsion Umits Report PECO-COLR P3012 Page 20. Rev.3 l

l TABLE 3 l

DESIGN LINEAR HEAT GENERATION RATE (LHGR ) LIMITS'

FUEL TYPE LHGR LIMIT GE13 14,4 kW/ft GE11 14.4 kW/ft SPC 9x9-A (LFA) 14.4 kW/ft

(

D# 4:

F l

l ' The LHGR limits provided above are the beginning of life (maximum) values. LHGR

limits as a function of fuel exposure are provided in the process computer data bank and COLR References (3) and (19).

. 'PEb0 Nuclear Fuel and Services Division PECO COLR-P3012  !

l P3C12 Core Operating Umits Report Page 21, Rev.3 TABLE 4 l

TURBINE BYPASS VALVE PARAMETERS  !

l l

TURBINE BYPASS SYSTEM RESPONSE TIME l Maximum delay time before start of bypass valve '

opening following generation of the turbine bypass 0.10 sec. ;l  ; ,, ,

valve flow signal 1" I we.

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

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

Minimum required number of bypass valves to maintain system operability 7 l s:Wdbto@c12r3. doc

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