ML20198P147

From kanterella
Jump to navigation Jump to search
Rev 0 to PECO-COLR-P3C12, COLR for PBAPS Unit 3,Reload 11, Cycle 12
ML20198P147
Person / Time
Site: Peach Bottom Constellation icon.png
Issue date: 08/13/1997
From: Carmody J, Payton S, Tusar J
PECO ENERGY CO., (FORMERLY PHILADELPHIA ELECTRIC
To:
Shared Package
ML20198P144 List:
References
PECO-COLR-P3C12, PECO-COLR-P3C12-R, PECO-COLR-P3C12-R00, NUDOCS 9711060288
Download: ML20198P147 (21)
v • d • e


Text

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

1

. PECO Nuclear FW and Servloes Division PECO COLR-PSC12 P3C12 Core Operating Umits Report Puge 1. Rev.0 i

I CORE OPERATING LIMITS REPORT FOR

, 1 PEACH BOTTOM ATOMIC POWER STATION UNIT 3 RELOAD 11, CYCLE 12 REVISION O Prepared By: 9- M Date: G) /2./97 S. I'. Payton Engineer Nuclear Design & Materials Branch Reviewed By: h Date:' bdfA

[F J. J. Tusar Engineer Nuclear Design & Materials Branch 4

Approved By: We Date:

  1. 7

/ J. M. Carmodyl Manager Nuclear Design & Materials Branch 28 fSNONk

F_ PECO Nuclear Fuel and Services Olvision PECO COLR P3Ct3

' P3013 Core Operating Umits Report Page 2. Rev.0 LIST OF EFFECTIVE PAGES Page(s) Revision 1 21 O I

l . -

' PECO Nuclear Fuel and Services Division P3C12 Core ONrating Limits Report PECO COLR P3012 t

Pa9e 3, Rev.0 INTRODUCTION AND

SUMMARY

k Unit 3 Cycle 12 (Reload 11):This report provides the following cycle specific para 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 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 es cpplicable limits of the plant safety analysis are met.

for the following conditions:This report provides the means for calculating the Opera All points in the operating region of the power / flow map including Maximum Exten 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 r. minimum powerlevelof 40%

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

. Feedwater 55*F Temperature Reduction (FWTR), to a maximum feedwater temperature' This report contains all thermallimit parameters related to the implementation of th Program Cycle 12. and Maximum Extended Load Line Limit Analyses (ARTS /MELLLA) for Pe this report was performed in accordance with PECO Ener FM 300. " Reload Core Licensing".

. PECO Nuclear fuel and Services Division PEco COLR-P3C12 P3012 Core Operating Umits Raport Page 4 Rev.0 i

M APLHGR t.lMITS 4

The limiting MAPLHGR value for the most limitir.g lattice (excluding natural uranium) of each fuel type as a function of average planar exposure is provided in Figures 1 through 4. These figures are used when hind calculations are required as specified in Reference (6). All MAPLHGR limits for each fuel type as a function of axiallocation and average planar exposure shall be less than or equal to the applicable limit vrlues for the respective fuel and lattice types to be in compliance with Technical Specification 3.2.1.

These limit values are specified in References (3), (4), (5), (16) and the process computer databank. The

, Si: mens Power Corporation (SPC) Lead Fuel Assemblies (LFAs) will be monitorod to the modified

' GE9B P8DWB32010GZ (Peach Bottom 2 Reload 8 bundle) MAPLHGR linsite per Rnferences (10) and (16). The ARTS based MAPLHGR power dependent multipliers (MAPFAC(P)) are provided in Figures 5

' cnd 6 Figure 5 is valid for seven or more (of nine) Turbine Bypass Valves (TBVs) in Serv!ce. Figure 6 is v; lid 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 power and flow dependent MAPLHGR multipliers were obtained from Reference (15).

MCPR LIMITS The Operating Limit MCPR (OLMCPR) for usa 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 time verification is required as per Technical Specification 3.1 A ' Control Rod Scram Times". Tau, a measure of scram time performance to notch position 36 throughout the cycle, is determined based on the cumulative scram time test results. The calculation of Tau shall be performed in accordance with site procedures.

S:parate MCPR values are presented herein for the following domains:

Core Flow s 100% of Rated, No FWHOOS/PVTR, TBVs In Service

, Core Flow > 100% of Rated, up to 110% of Rated, With or Without FWHOOS/FWTR, TBVs In-i Service

. Core Flow s 100% of Rated, FWHOOS/FWTR, TBVs In Service

. Turbine Bypass talves Out-of Service (TBVOOS), 3 or raore out of service, With All Other Domains The OLMCPR values are documented in Reference (2) for the GE11 and GE13 fuel designs and Reference (10) for the SPC LFAs.

The ARTS based power dependent MCPR limits. OLMCPR(P), for use in Technical Specification 3.2.2 cre 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.

The OLMCPR(P) values bokw the turbine scram bypass power are dncumented in Reference (15).

OLMCPR(P,F) curves were obtained from References (7) and (15).

-,- ,, , -. , , - - . - - - - , - n a e,,, - - , -m

' PbCO Nuclear Fuel and Servloes Division P3C12 Core Operating Umits Report PECO COLR.P3C12 Page 5. Rev.0 OVERALL GOVERNING MCPR AND MAPLHGR LIMITS 1

ARTS provides for power and flow dependent thermallimit adjustments and multipliers which allow more reliable administration of the MCPR and MAPLHGR thermal limits. At any given power state, all four limits are to be determined: MAPFAC(P), MAPFAC(F), OLMCPR(P), and OLMCP Figures 5 through 11, inclusive (per References (7) and (15)]. The most limiting MCPR and the m limiting MAPLHGR (maximum of OLMCPR(P) and OLMCPR(F) and minimum of MAPLHG MAPLHGR(F)) for a given (P,F) condition will be the goveming limits. The OLMCPR for e determined by the cycle specific fuel reload analyses in Reference (2). Rated MAPLHGR values j

composite of results obtained from bundle specific thermal mechanical and emergency core t system analyses. Supporting documentation for the ARTS based limits is provided in Reference ROD BLOCK MONITOR SETPOINTS The RBM power biased Analytical Limits, A!!owable 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 documenta References (2), (11) and (12).

~

LINEAR HEAT GENERATION RATES 4

The beginnhg of life (maximum) design LHGR limits for each fuel type for use in Technical Spe 3.2.3 are provided in Table 3. Conservative LHGR values as a function of fuel exposure are provide the process computer data bank and Reference (3). The bases for these LHGR values are documented in References (6) and (10).

STEAM BYPASS SYSTEM OPERABILITY The operability requirements for the steam bypass system are governed by Technical Specification 3.

i 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 Ta

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

REFERENCES

1) "Tachnical Specifications for Peach Bottom Atomic Power Station Unit 3", Docket No. 50-278, Appendix A to License No. DPR-56,
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.
4) " Lattice Dependent MAPLHGR Report for Peach Bottom Atomic Power Station Unit 3 Reload 10 Cycle 11",24A5175AA, Revis!on 0, September 1995.
5) " Lattice Dependent MAPLHGR Report for Peach Bottom Atomic Power Station Unit 3 Reload 9 Cycle 10",23A7215AA, Revision 1, March,1994.

l -

PIC0 Nuclear Fuel and Serviose Olvlelon PECO COLR P3C12

'PSC12 Core operating Umits Report Pete 4. Rev.0

6) "deneral Electric Standard Aoptication 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 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 Requirements", 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 B 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 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.

,w

. PECO Nuclear Fuel and Serv 6ces Division PECO COLR P3C12 P3C12 Core Operating Limits Report Page 7. Rev.0 4 1

,. . FIGURE 1 l MAXIMUM AVERAGE PLANAR LINEAR HEAT GENERATION RATE (MAPLHGR) VERSUS AVERAGE PLANAR EXPOSURE FUEL TYPE GE13 P9DTB40013GZ 100T 146 T o..,

l i is. f , [HIS FIGURE IS REFFERED TO BY TECHNICAL SPECIFICAflON 3 2.1 l

\ \ \

3

"- x I l

4 .

I x\ <

i l

i  :: " ' i x i 6.4 I

I ... ,

t.0 N

s.8 l

i

['  !

i.e 3.0 n.4 10.9 it.t 48.6 15.0 10.0 36.4 40.9 45.0 18.9 55.0 40.0 Average Planar Exposure (GWd/ST)

Avg Plan Avg Plan Avg Plan Exposure MAPLHGR Exposure MAPLHGR Exposure MAPLHGR 4

(GWd/ST) (k"'Lt (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

, e -- - - - , . , , -,--------,w - - - >

, PECO Nuclear fuel and Swvices Division PECO COLR PSC12 P3C12 Core Operating Umits Report Page 8, Rev.0

, FIGURE 2 i MAXIMUM AVERAGE PLANAR LINEAR HEAT GENERATION RATE (MAPLHGP.) VERSUS AVERAGE PLANAR EXPO!)URE FUEL TYPE GE11 P9 HUB 40513GZ1 100T 146 T i.... . . . . . .

is.

' THIS FIGURE IS REFFERED TO BY j TECHNICAL SPECIFICATION 3 2.1 I u.. I

  1. N

_ u.e

/ x E \

is..

=

... \

... \

7.4 3.s 1.1 10.0 15.9 30.5 88.9 30.0 31.6 40.0 .l.0 40.5 ll.0 St.e 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 0.2 10.48 8.0 11.45 30.0 10.22 1.0 10.59 9.0 11.57 35.0 9.62 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

l .

l

^ PECO Nuclear Fuel and Services Division PECO.COLR#3C12 P3C12 Core Operating Umits Report Page 9. Rev.0

. FIGURE 3 MAXIMUM AVERAGE PLANAR LINEAR Ff.AT GENERATION RATE (MAPLHGR) VERSUS AVERAGE PLANAR EXPOSURE FUEL TYPE GE11 l'9 HUB 367110Z 100M 146 T I

ss.. ,/  : THIS FIGURE IS REFFERED TO BY TECHNICAL SPECIFICATION 3 2 i I

ii..

\

x 5ie.. N 3

~

\

... \,

... \

\

\

l

... ... .... ii.. .... .... .... ii.. .... . .. .... is,. ....

Average Planar Exposure (GWd/ST)

Avg Plan Avg Plan Avg Plan Exposure MAPLHGR Exposure MAPLHGR Exposure MAPLHGR (QWd/ST) (kEtl (GWd!ST) (kW/ft) (GWd/ST) (kW/ft) 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 17.5 12.07 55.0 6.93 6.0 11.97 20.0 11.73 57.64 6.56 4

l PECO Nuclear Fuel and Services DMalon PECO-COLRMC12 P3C12 Core Operating Limits Report Page 10. Rev.0

,. FIGURE 4 MAXIMUM AVERAGE PLANAR LINEAR HEAT GENER ATION RATE (MAPLHGR) VERSUS AVERAGE PLANAR EXPOSURE FUEL TYPE SPC 9x9 A (LFA)

.._. q .

I i

THIS FIGURE is REFFERED TO Bf

, TECHNICAL SPECIFICATION 3 2.1 13.0 '

7 i

11.0 7

g 3....

I... \,

... \

1.9 0.0 5.9 14.0 15.4 39.9 38.6 St.6 St.6 46.9 45.0 59.0 85.4 Average Planar Exposure (GWd/ST)

Avg Plan Avg Plan Av0 Plan Exposure MAPLHGR Exposure MAPLHGR Exposure MAPLHGR (GWd/ST) (kW/ft) (GWd/ST) (kW/tt) (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 8.29 4.0 11.58 12.5 12.85 51.06 5.45 5.0 11.83

k PECO Nuclear Fuel and Serv 6ces Divlelen PRC040LR PSC12 P3C12 Core Opereting Limits Repori Page 11. Rev.0 FIGURE 5 POWER DEPF.NDENT MAPLHGR MULTIPLIER MAPFAC(P)

THIS FIGURE IS P.EFERHED TO BY TECHNICAL SPECIFICATION 3.2.1 VALID FOR 7 OR MORE TBVs IN SERYlCE 1.3

1. 0 -

E U

on

0. 6 -

$=

0 u

e g s 60% Flow 5 '

- on O.5499 MAPLHOR(P) . MAPFAC(P)' MAPLHGRsta C

e MAPLHORatd - Standard MAPLHGR Lmits 0.451 l C l 0,418 For 25% > P : No Thermad Umsta Marutoreg Required

( 0.4 - 0.388 No Urmts Speedied For 25% s P < 30% : MAPFAC(P) . 0.511 + 0.012 * (P . 30%)

w For s 60% Core Flow l l MAPFAC(P) = 0 418 + 0 006 ' (P

  • 30%)

l l > 60% Fk'w For > 60% core Fkm A '

l l For 30% s P : MAPFAC(P) . 1.0 + 0 00643 * (P .100%)

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

l .

PECO Nuclear fuel and Serv 6ces Division PIC040LR PSC12 P3C12 C0re Operating Umits Report Pa0s12.Rev.0 FIGURE 6 POWER DEPENDENT MAPLHGR MULTIPLIER MAPFAC(P)

THIS FIGURE IS REFERRED TO BY TECHNICAL SPECIFICATION 3.2.1,3A.1 AND 3.7.6 VALID FOR 3 0R MORE TBVs OO3 1.2 J

1. 0 < ,

E E

$ 0 .0 A

3 u

E g s 60% Flow o

m O. 499 MAPLHGR(P) . MAPFAC(P)' MAPLHrP.sta N

e 0.451

  • iMAPLHORstd . Standard MAPLHOR Umsts

{

h 0.418 IFor 25% > P : No Thermal Umsta Monstormg Rmunteo

( 0.4 ' O.388 No Umsts Specifed b .

y For 25% s P < 30% : MAPFAC(P) = 0.611 + 0 012 ' (P . 30%)

p

  • For s 60% Core Flow l

g MAPFAC(P) = 0.418 + 0 006 ' (P . 30%)

l l > 60% Flow For > 60% Core Flow a . .

For 30% s P : MAPFAC(#) . 1.0 + 0.00643 * (P .100%)

: (

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

, PEb0 Nuclear Fueland Services ion t PECO COLR P3C12 P3C12 Core Operating Umits Repon Page 13.Rev.0 FIGURE 7 FLOW DEPENDENT MAPLHGR MULTIPLIER MAPFAC(F)

THIS FIGURE IS REFERRED TO BY TECHNICAL SPECIFICATION 3.2.1 VALID FOR TWO LOOP RECIRC FLOW 1.1 I

I i

l l

l 0.9-C G $

h l a 0.8 -

a <

u. .

MAPLHGR(F) = MAPFAC(F)

5 M 6.PFACl(F) = (Af ' We /100 + BI). OR g = 1.0; whichever is lower lE 0.6- Wc = % Rated Core Flow 0.5 72 Al = 0.6682. Bf = 0.5055 0.5 -  ;

0.4  ; l l l l  ;  ;

l  ;

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

, PECO Nuc4eer Fuel and Services Olvision PEC040VW3C12 PSC12 Core Operating Umi s Report Pege 14, Rev.0

. 4 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 t

1 --

0.9 -- ,

C  !

6 t  :

I 0.8 -

MAPLHGR(F) = MAPFAC(F)

, 0.7 -- MAPLHGRstd = Standard MAPLHGR Limits 0

5 MAPFACf(F) = (At

  • We l 100 + Bf), OR g = 0.9; whichever is lower 2

0.6 -- We = % Rated Core Flow 0.572 A1 = 0.6682, Bt = 0.5055 {

l 0.5 --

{

0,4 l l l l l l l 10 20 30 40 50 6b 70 80 90 100 110 Core Flow (% Rated) m

TABLE 1 .

3;g OPERATING LIMIT MINIMUM CRITICAL POWER RATIO (OLMCPR ) -

n Use in conjunction with Figures 9,10, and 11 %o Add 0.01 to the OLMCPR when in Singio Loop Operation .

{E.

This Table is referred to by Technical Specification 3.2.2,3.4.1 and 3.7.6 s100% OF RATED ANY a

"c.R CORE s100% OF RATED > 100% OF RATED FLOW gus N S/ NO YES OR NO YES YES OR NO TBVs IN SERVICE IN ____________ OUT

_________ __ __IN__-SERVIC E

_______ __ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ __-SERVICE .___ _ -OF_ SERVICE

_ _ _ _ e Opt. B Opt. A Opt. B Opt. A S Opt. B Opt. A Opt. B Opt. A 1.38 1.35 1.39 1.35 1.38 1.40 1.45 Reload 10  : MOC 1.35 GE11 Only 1.45 1.38 1.46 1.38 1.46 1.45 1.53 l EOC 1.37 1.38 1.34 1.39 1.33 1.38 1.40 1.45 Reload 9 GE11 l MOC 1.33 1.38 1.46 1.38 1.46 1.45 1.53 and GE13 l EOC 1.37 1.45 1.42 1.39 1.43 1.39 1.42 1.44 1.49 SPC MOC 1.39

  • 1.49 1.42 1.50 1.42 1.50 1.49 1.58 I. EOC 1.41 NOTES: 1) Opt. B: Tau _-0.0
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.,1.35).

n

4) MOC: Cycle exposure from BOC to EOR-2000 mwd /ST S
5) EOC: Cycle exposure from EOR-2000 mwd /ST to EOC u9
6) FWHOOS: Feedwater Heater Out-of-Service, maximum 55 T 3o eO
7) FWTR: Feedwater Temperature Reduction, maximum 55 T g

,5

8) TBVOOS: Turbine Bypass Valves Out-of-Service (3 or more TBV's OOS)
n3

.t

  • QN
  • PECO Nuclear Fuel and Services Divleion PSC12 Core Operseng Umits Report PECO.COLR P3C12 Page 16. Rev.0 FIGURE 9 POWER DEPENDENT MCPR LIMIT ADJUSTMENTS AND MULTIPLIERS THIS FIGURE IS REFERRED TO BY TECHNICAL SPECIFICATION 3.2.2 VAllD FOR 7 OR MORE TBVs IN SERVICE 3.25 3.2 - .

l l

3.0 -

OPERATING UMIT MCPR(P) = Kp

E 29I 3r > 60% Flow lFOR Pc25% NO ;UMITS NO SPECIFIED THERMAL UMIT MONITORING REOUIRED Q-i.e - 2,78 '

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

O OLMCPR = Kbyp + SLOPE '(30%. P)

2. 6 ' l l Kbyp = 2.26 FOh s 60% CORE FLOW s e
  • = 2.91 FOR > 60% CORE FLOW SLOPE = 0.104 FOR s 60% CORE FLOW pI , = 0068 FOR > 60% CORE FLOW FOR 30% s P < 45% : Kp = 128 + 0 0134 * (45% . P) 5 60*/. Row

{ , 2.26 = FOR 45% s P < 60% : Kp = 1.15 + 0 00867 * (60% . P) 3.3 -

l FOR 60% s P : Kp = 100 + 0 00375

  • f100% . P)

ABSOLUTE { {

3.0 q MULTIPLIER ',

l

{

k l l g s...  :  :

5

^  !!

o. l l E, t.s .

l s.w

1. . .

g i i

1. <

1  :

E i i 1.0 0 10 20 30 40 50 s0 70 00 90 100 Power (% Rated)

' PECO Nuclear Fuel and Serv 6ces Division PECO @ UW4C12 P3C12 Core Operating Umits Report Page 17,Rev.G 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

3. 3 - ,

g OPERATING UWT MCPR(P) . Kp ' OLMCP9(100) 3,,, l FOR P<25% : NO THERMAL UMIT MONITORING REOUIRED NO UMITS SPECIFIED

> 60% Flow 2.91 FOR 25% s P < Pbypass :(Pbypass = 30%)

B:,a*p, l OLMCPR(P) . Kbyp + SLOPE ' (30% P) 2.78 (Q ,

l l

Kbyp . 2 26 FOR s 60% CORE FLOW Kbyp . 2 91 FOR > 60% CORE FLOW SLOPE .0104 FOR 5 60% CORE FLOW

$ 2.s . SLOPE . 0 068 FOR > 60% CORE FLOW O l l FOR 30% s P < 45% ; Kp .128 + 0 0134 * (45% . P)

.4 FOR 45% s P < 60% : Kp .1.15+0 00867 * (60WP) k ' FOR 60% s P : Kp .1.00+0 00375 * (100%P) l 2 .26 a.: . s 60% Flow l l l l ABSOLUTE l l 2..

MULTIPLIER l l

s. . .

$ t.o .  !  !

e' l l a l l E 1.s . l l

  • l l

,.E 1.4 - ' ' h s l l E

g1.. .

1 l l I

3 1 .. '

o to ao so ao so so no to so too Power (% Rated)

l PECO Nuclear Fuel and Serv 6ces Division PECOCOLR PSC12

' P3012 Core Operating Umits Report Page 18,Rev.0 FIGURE 11 FLOW DEPENDENT MCPR LIMITS OLMCPR(F)

THIS FIGURE IS REFERRED TO BY TECHNICAL SPECIFICATION 3.2.2 f

! 2 1.9--

For We (% Rated Core Flow) < 40%

]-- OLMCPR(F) = (Af

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

' ~

For We (% Rated Core Flow) a 40% .

OLMCPR(F) = (Af

  • Wc. 00+Bf), OR 1.25:

whichever is greater E'" 1.569 E .

0 1.5 -- Af = - 0.5526 * (1.11/1.07) = - 0.5733 Bf = 1.6311 * (1.11/1.07) = 1.6921 l 1.463 l  ; '

1.4 -- -

l l l l l l l 1.3-- ' '

; 1.26 l l l 1.2 -- l l l l l l l l l l l l I '

1.1  ! l l l l 10 20 30 40 50 60 70

  • B0 90 100 110 Core Flow (% Rated)

PECO Nuclear Fuel and Services Division

'4CO COUI P3C12 P3012 Core Operating Umits Report l Page 19. Rev.0 4 .- TABLE 2 l

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 LIMIT'" VALUE LIMIT 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

  • Inop N/A N/A < 1.70 *

< 1.40

  • Downscale 2 1.0% 2 2.5% < 1.70
  • 2

< 1.40

  • Bypass Time Delay * --- -- ----

(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 PO'#ER 2 2G.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).

--, , 4 - , - - -

1 1

P!!CO Nucieer Fuel and Services Divleion #

PECOCOLRf3C12 PE12 Core Operating Umits Report Page20.Rev.0 TABLE 3 DESIGN LINEAR HEAT GENERATION RATE (LHGR ) LIMITS' FUEL TYPE .LHGR LIMIT I

GE13 14.4 kW/ft GE11 14.4 kW/ft SPC 9x9 A(LFA) 14.4 kW/ft n ,

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

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

, PECO Nuclear Fuel and Sendees DMalon L PECO COGP3C12 3C12 Core Operating Umits Report Page 21.Rw.0 E

TABLE 4 ,

TURBINE BYPASS VALVE PARAMETERS 8

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

\ valve flow signal k

Maximum time after generation of a turbine bypass valve ficw 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

.h , na - -ApfQf:4 s:WtteotrWc12r0. doc

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

Retrieved from "https://kanterella.com/w/index.php?title=ML20198P147&oldid=3003604"