ML18038B973

Cycle 10 Colr.

ML18038B973
Person / Time
Site:	Browns Ferry
Issue date:	09/26/1997
From:	Bruce A, Keys T, Riley E TENNESSEE VALLEY AUTHORITY
To:
Shared Package
ML18038B972	List: ML18038B971 ML18038B973
References
TVA-COLR-BF2C10, TVA-COLR-BF2C10-R, TVA-COLR-BF2C10-R00, NUDOCS 9710210148
Download: ML18038B973 (50)

Text

TVANuclear Fuel t

Core Operating Limits Report TVA-COLR-BF2C10 Revision.0, Page 1 Browns Ferry Nuclear Plant Unit 2, Cycle 10 CORE OPERATING LIMITS REPORT (COLR)

TENNESSEE VALLEYAUTHORITY Nuclear Fuel Division BWR Fuel Engineering Department Prepared By: Da~e:

Earl.E. Riley, Engineering Specialist BWR Fuel Engineering Verified By Alan L. Bruce, Nuclear Engineer BWR Fuel Engineering

.Approved By: Date T; A.'Keys, Ma ger BWR Fuel Engineering Reviewed By: Date:

eactor Engineering Supervisor Reviewed. By: Date:

PORC Chairman 97i02iOi48 9'7iOi5 PDR ADQCK 050002bO P PDR

0 i' TVANuclear Fuel l

Core Operating Limits Report TVA-COLR-BF2C10 Revision 0, Page 2 Revision Log Revision Date D~escri tion AfFected Pa es 0 9/25/97 Initial Release All

r- '4 TVANuclear Fuel 1 Core Operating Limits Report TVA-COLR-BF2C10 Revision 0, Page 3'.INTRODUCTION This Core Operating Limits Report for Browns: Ferry Unit 2, Cycle 10 is prepared in accordance with the requirements of Browns Ferry Technical Specification 6;9.1.7. The core operating limits presented here were developed using NRC-approved. methods (References 1 and.2). Results from the reload analyses for Browns Ferry Unit 2, Cycle 10 are documented in Reference 3.

The following core operating limits are included in this. report:

a. Average Planar Linear Heat Generation Rate (APLHGR) Limit (Technical Specification 3.5.I)

'b. Linear Heat Generation Rate (LHGR) Limit (Technical Specification 3'.S.I)

c. Minimum. Critical Power Ratio Operating 'Limit (OLMCPR)

(Technical Specification 3.5.K/4.5.K)

d. Average Power Range Monitor (APRM) Flow Biased Rod'Block Trip. Setting

,(Technical Specification:2.1.A.l.c and Table 3.2:C)

e. Rod Block Monitor (RBM) Trip Setpoints (Technical, Specification Table 3.2:C)

il

, ~

TVANuclear Fuel TVA-COLR-BF2C10 Core Operating Limits Report Revision'0, Page 4

,2. APLHGR LIMIT(TECHNICALSPECIFICATION 3.5."I)

The APLHGR limits for full power and flow, conditions for each type of fuel as a function of exposure are shown in Figures 1-8. The APLHGR limits for the GE9B, GE11 and GE13 assemblies are for the most'limiting lattice (excluding natural uranium) at each exposure

,point. The specific values for each lattice are given in Reference 4.

These APLHGR limits are adjusted for off-rated power and flow conditions using the ARTS factors, MAPFAC(P) and MAPFAC(F). The reduced power factor, MAPFAC(P), is given in Figure 9. Similarly, adjustments for reduced flow operation are performed using the MAPFAC(F) corrections given in Figure 10. Both factors are multipliers used to reduce the standard APLHGR limit. The most limiting power-adjusted or flow-adjusted value is taken as. the APLHGR operating limit for, the ofF-rated condition.

Ik ll TVANuclear Fuel TVA-COLR-BF2C10 Core Operating Limits Report Revision 0, Page'5

3. LHGR LIMIT(TECHNICALSPECIFICATION 3.5.J)

The LHGR limit for unit 2 cycle 10 is fuel type dependent, as shown below:

GE7B (BP8X8R) 13.4 kw/ft GE9B (GE8X8NB) 14.4 kw/ft GE11 14.4 kw/ft GE13 14;4 kw/ft

0 I'

TVANuclear Fuel TVA-COLR-BF2C10 Core Operating Limits Report Revision 0, Page 6 4; OLMCPR (TECHNICALSPECIFICATION 3.5.K/4.5.K)

.a. The MCPR Operating Liinitfor rated power and flow conditions, OLMCPR(100), is equal to the fuel type and exposure dependent limit shown in Figures 11, 12, 13, and

14. The actual OLMCPR(100) value is dependent upon the scram time testing results, as described below:

Zme ZB

= 0.0 of whichever is greater.

ZA ZB

'5 = 0.90 sec (Specification 3.3.C. 1 scram time limit to 20%

insertion from fully withdrawn )

i

= 0.710 + 1.65 '

N ~

Z~ (0.053) n n

g i=i zi Zave n

where; n = Number of surveillance rod tests'performed to date in cycle (including BOC test).

Zi = Scram time to 20% insertion from fully withdrawn of.the i foil.

N = Total. number of active rods measured in Specification 4.3.C. 1 at BOC.

b. For the performance of Surveillance Requirement 4.5.K.2.a (prior to'initial scram time measurements for the cycle),

'6 = 1.0

c. For the performance of Surveillance Requirement 4.5.K.2.b, 'C,shall. be determined'in accordance with 4.a above.

d..For off-rated power and flow conditions, power-adjusted and flow-adjusted operating limits. are determined from Figures 15 and 16, respectively. The most limiting power-dependent or flow-dependent value is taken as. the OLMCPR for the of-rated condition.

II TVANuclear Fuel Core Operating Limits Report'VA-COLR-BF2C10 Revision 0, Page 7

5. APRM FLOW BIASED ROD BLOCK TRIP SETTING (TECHNICAL SPECIFICATION 2.1.A.l.c AND TABLE 3.2.C)

The APRM Rod Block, trip setting shall be:

'SRB 5 (0;66W+66Ão) Allowable Value SRB g (0 66W + 64') Nominal Trip Setpoint (NTSP) where:

SRB.=:Rod Block setting in percent of rated thermal power (3293 MWt)

W = Loop recirculation flow rate in percent of rated The APRM Rod Block trip setting is clamped at a maximum allowable value of 115 jo (corresponding to a NTSP of 113/o).

Ih TVANuclear Fuel TVA-COLR-BF2C10 Core Operating Limits Rcport Revision 0, Page 8

6. ROD BLOCK MONITOR (RBM) TRIP SETPOINTS (TECHNICALSPECIFICATION TABLE 3.2.C)

The RBM trip setpoints and applicable power ranges, shall be as follows:

LPSP 27% 25%

IPSP 62o/ 60%

HPSP 82% 80%

LTSP - unfiltered 121 7% 120 0%

- filtered, 119 0% (1) (2) 120.7%

ITSP - unfiltered 116.7% 115.0%

- filtered 114.0% (1) (>)

115.7%

HTSP - unfiltered 111.7% 110.0%

- filtered. (1) (2) 1.10.9% 109.2%

DTSP 90% 92%

Notes: (1) These setpoints are based upon a MCPR operating limit of 1.34 using a safety limit of 1.10. This is consistent with a MCPR operating limit of 1.30 using a safety limit of 1.07, as reported in references 6, 7, and 8.

(2) The unfiltered setpoints are consistent with a nominal RBM filter setting of 0.0 seconds (reference 8). The filtered setpoints are consistent with a nominal RBM filter setting < 0.5 seconds (reference 7).

Ik TVANuclear Fuel TVA-COLR-BF2C10 Core Operating Limits Report Revision 0, Page 9

7. REFERENCES

1. NEDE-24011-P-A-13, "General Electric Standard Application for Reactor Fuel", August 1996.

2. NEDE-24011-P-A-13-US, "General Electric Standard Application for Reactor Fuel (Supplement for United States)", August 1996.

3. Jl 1-03144SRL'R Rev. 1, "Supplemental Reload Licensing Report for Browns Ferry Nuclear Plant Unit 2 Reload 9 Cycle 10", September 1997.

4. Jl 1-03:144MAPL Rev.'0, "Lattice-Dependent MAPLHGR Report for Browns Ferry Nuclear Plant Unit 2 Reload 9 Cycle 10", August 1997.

5. NEDC-32774P Rev; 1, "Safety Analyses for Browns Ferry Nuclear Plant Units 1, 2, and 3 Turbine Bypass and End-of-Cycle Recirculation Pump Trip Out-Of-Service", dated September 1997.

6. NEDC-32433P, "Maximum Extended Load Line Limit-and ARTS Improvement Program Analyses for Browns Ferry Nuclear Plant Unit 1, 2, and 3", dated April 1995.

7. EDE-28-0990 Rev. 3 Supplement F, "PRNM (APRM, RBM, and RFM) Setpoint Calculations [ARTS/MELLL(NUMAC) - Current Rated Condition] for Tennessee Valley Authority Browns Ferry Nuclear Plant", dated Sept. 1997.

'8. EDE-28-0990'Rev. 2 Supplement F, "PRNM (APRM, RBM, and RFM) Setpoint Calculations [ARTS/MELLL(NUMAC) - Current Rated Condition] for Tennessee Valley Authority Browns Ferry Nuclear Plant", dated, Sept. 1997.

9. GE Letter LBAt: 262-97-133, "Browns Ferry Nuclear Plant Rod Block Monitor Setpoint Clarification - GE Proprietary Information", dated September 12, 1997.

,[L32 970912 800]

4l l

TVANuclear Fuel TVA-COLR-BF2C10 Core Operating Limits Report Revision 0, Page 10 Figure 1 APLHGR Limits for Bundle Type GE13-P9HTB384-12G4.0 (GE13) 15 14 13 12.

UNACCEPTABLE OP E RATION 10 9

,8 lY ACCEPTABLE OPERATION 7

(o

o. 6 0

00 10.0 20.0 30.0 40.0 50.0 Cycle Exposure (GWDIST)

Most Limiting Lattice for Each Exposure Point

AVe'rage::Plai1arp,":.:'::i,,:,."L'HGR::;-;!:;:i);; ,::; Ave'raqe,:P.lanai~~:.;.:::;::,'I HGR;:;"Si ':,;Average'.,Planar)~::-;::L'HGR"~

",>".';;:.:",'.;.Ei'Pastire'.:::,":,::;,:'.I:;,::-;'::;:-:I.'im'i':,.':.;

0.0 10.09 7.0 11.71 25.0 10.6 0.2 10.15 8.0 11.95 30.0 9.99 1.0 10.31 9.0 12.16 35.0 9.39 2.0 10.52 10.0 12.28 40.0 8.76 3.0 10.75 12.5 12.16 45.0 8.11 15.0 11.88 50.0 7.44 4.0 5.0 6.0 10.99 11.25 11.48 17 20.0 51.1.56 11.24 55.0 55.98 6.60

0 TVANuclear Fuel TVA-COLR-'BF2C10 Core Operating Limits Report Revision 0, Page 11 Figure 2 APLHGR Limits for Bundle Type GE11-P9HUB366-12G4.0 (GE11) 15 14 13 12 UNACCEPTABLE OPERATION 10 9

p E, 8 ACCEPTABLE OPERATIO N 7

U

o. 6 5

I 4

0 00 10.0 20.0 30.0 40.0 50.0 Cycle Exposure (GWDIS'f)

Most Limiting Lattice for Each Exposure Point

Avera'ge.

.:Pla'vari,::::::::,';.:,":,:.;".,::ILHGR(':,::.:,' ';;,":Averige':.;Plariar",',::,:::,'-:.:::.:;,':.".:L'HGR:::;.":  !:"Average Plaiiar@k5'.:::LHGRP~

'j~-.;j.EXji0S4rP ~:;-"~~"'~:;;(jib,imit;;-'(;;;',':

!'

::, 6WDIS.::":-;::;:::::,:.:';,',::"::::,":::. kwlft:,": '.'!.'""A" GWDIS :>"."I'c."."': i""'$ft

'0.0 9.55 7.0 11.39 25.0 10.51 0.2 9.62 8.0 11.67 30.0 9.84 1.0 9.80 9.0 11.81 35.0 9.19 2.0 10.05 10.0 11'.95 40.0 8.55 3.0 10.32 12.5 11.92 45.0 7.91 4.0 10.58 15.0 11.72 50.0 7.26 5.0 10.84 17.5 11.48 55.0 6.59 6.0 20.0 11.20 56.17 6.42

41 TVANuclear Fuel TVA-COLR-BF2C10 Core Operating Limits Rcport Revision 0, Page 12 Figure,3 APLHGR Limits for Bundle Type GE11-P9HUB367-14GZ (GE11) 15 14 13 UNACCEPTABLE OPERATION 10 9

8 ACCEPTABLE OPERATIO N ts' 7 5

,3 0

00 10.0 20.0 30.0 40.0 50.0 Cyme Exposure (GWDIST)

Most Limiting Lattice for Each Exposure Point

~A'aerage;

,PIanii.':.:,':,~F(!:-::.'ILHGR:,",.;:.j:;  ;!Average::Planar~"';:'lHGR(j

<

:::;"',,BXfiostirA";:I:;:,:::>>;.:;;-.;,:,';;;:::::Limit;,:,::,":;.;

'.4!'= GIND'18 .,';:.:;.:-;:":"'..'; 6'ih:,-::-":.:

0.0 9.18 7.0'.0 11.31 25.0 10.51 0.2 9;27 11.67 30.0 9.84 1.0 9.45 9.0 11.81 35.0 9.19 2.0 9.'72 10.0 11.95 40.0 8.55 3.0 10.00 12.5 1,1;92 45.0 7.91 4.0 10.30 15.'0 11.72 50.0 7.26 10.62 17.5 1'1.48 55.0 6.59 5.0'.0

.10.95 20.0 11.20 56.17 6.42

ih 4l>>

TVANuclear Fuel TVA-COLR-BF2C10 Core Operating Limits Report Revision 0, Page 13

'Figure 4 APLHGR Limits for Bundle Type GE9B-PSDWB319-9GZ (GESXSNB) 15 14 13 12 UNACCEP TABLE OPERATION 10 9

E 8 ACCEPTABLE OPERATION 7

U

o. '6 5

4 0

0.0 10.0 20.0 30.0 40.0 50.0 Cycle Exposure (GWDIST)

Most Limiting Lattice for Each Exposure Point

';";,'Averige':Planar-::.:::,"'."".K'Ak':HGRg:;-.'";;:;'.-,:,'Ayera'ge::Planar Sg"':::,LHSR@m

,;",'

EIt'P0SMri~

;

,

;:.".,';:;",':::,:,,",:.','.;.Limit>>:,'-.",'.-:.:

'.".-':< Geois <l..':""::..':::.>> itWe;<>>::.'::.>>~ GWDIS..";k:<4k@VIft;.

0.0 11.64 7.0 12.49 35.0 10.41 0.2 11.68 8.0 12.65 45.0 8.81 1.0 11;77 9.0 12.77 51.2 5.91 2.0 11.88 10.0 12.86 3.0 12.01 12.5 12.86 4.0 12.'12 15.0 12.62 5.0 12.'22 20.0 12.06 6.0 12.32 '25.0 11.47

Ik TVANuclear Fuel 'VA-COLR-BF2C10'evision Core Operating Limits Report 0, Page 14 Figure 5 APLHGR Limits for Bundle Type GE9B-P8DWB325-10GZ (GE8XSNB) 12'BLE

.15 14 13 UNACCEPT OPERATIO 10 9

E 8

ACCEPTABLE OPERATION 7

(o x

o. 6 4

0 00 '0.0 20.0 Cycle Exposure (GWDISTI 30.0 40.0 50.0 Most Limiting Lattice for Each Exposure Point

-AVera96::PJaltarjj,.-:,:...jLHGR.:'!.:':::':: ,'j'Average'::Planar"',.',>>.".":I;."-",;L'HGR~:, 'Qa":Planar'~:.='.;.".:'.LHGR@

0.0 10.97 7.0 12.23 35.0 10.12 0.2 11.00 8.0 12.35 45.0 8.60 1.0 11.11 9.0 12.46 50.27 5.92 2.0 11.31 10.0 12.58 3;0 11.54 12.5 12.58 4.0 1-1.79 15.0 12.35 5.0 11.97 20.0 11.86 6.0 12.10 25.0 11.33

Ib TVANuclear Fuel TVA-COLR-'BF2C10 Core Operating Limits Report Revision 0, Page 15 Figure 6 APLHGR Limits for Bundle Type GE9B-PSDWB326-7GZ (GE8X8NB) 15 14 13 UNACCE PTABLE'OPE RATION 12.

10 9

E 8 ACCEPTABLE OPERATION 7

U'.

6 5

3 0

.0 0 10.0 20.0 30.0 40.0 Cyde Exposure (GWD/ST)

Most Limiting Lattice for Each Exposure Point Av'clay'e::Planar,,;';,'g.::::.'.;::.LHGR;":.::::":;.',? ;':,'Avera9e;PIartar'-:;::.:, ~.;:: LHGR:::;',': :;"."Averar'Ie::Pfatla'r,,:;.'.';>j'.::,LHGR;g

,:.,i',:i!!i'Ntf)IS'T,'i!i:.'":i:::.k$  ::l':,'.-'.:'; tei'ilft 'i" ": ~: 'GWDI8T. S.".'5Nh>>

ki7iilft,"..'.0 11;45 7.0 12.31 35.0 10.15 0.2 11.47 8.0 12.41 45.0 1.0 11;55 9.0 12.51 50.49 5.93 2.0 11.70 10.0 12.63 3.0 11.87 12.5 12.64 4.0 12.01 15.0 12.41 5.0 12.13 20.0 11.91 6.0 12.22 25;0 11.35

If .l TVANuclear Fuel TVA-COLR-BF2C10 Core Operating Limits Report Revision 0, Page 16 Figure 7 APLHGR Limits for Bundle Type BP8DRB301L (BP8X8R) 15 14 UNACCEPTABLE OPERATION 13 12 10 ACCEPT ABLE OP ERATION E 8 7

U 0

0.0 5.0 10.0 15.0 20.0 25.0 30.0 35.0 40.0 Cyde Exposure (GWDIST)

';,IAVersgj;Pjariar:,'";,.;"..::.',",:>,.l-,;;;:l.'HOT;,".,'.: ':,;.'Aspera'ge,::Phriat;,,;,':'.g,.K:.'::.'::,1',HGR;:".:,-"..:.'.

)K. k'0:; Eltp 0$ tt fe jNK@j~c@x~8l Llrtt It 0(;

.'-':;:.'::-."'GV'io'is 'kwi8:J.":

'""M:.3'.".':::.; ',!,"')'GiwoiS:.':~,>>'>>",."."~)'k4Ni !

0.0 11.32 7.0 11.98 35.0 10.82 0.2 11.33 8.0 12.03 43.52 9.17 1.0 11.40 9.0 12.11 2.0 11.50 10.0 12.19 3.0 11.61 12.5 12.34 4.0 11.73 15.0 12.47 5.0 11.86 20.0 12.58 6.0 11;93 25.0 12.03

Ii

'I e

TVANuclear Fuel TVA-COLR-BF2C10 Core Operating Limits Report Revision 0, Page 17 Figure S APLHGR Limits for Bundle Type BP8DRBZ99 (BP8X8R) 15 14 UNACCEPTABLE OPERATION 13 12' 10 ACCEPTA BLE OPERAT ION 4

3' 0.0 5.0 10.0 15.0 20.0 25.0 30.0 35.0 40.0 Cycle Exposure (GWD/ST)

.,

:Average'.Planar'.-".-."$ <-'"ILHGR;~j~.:~IAvemge::Planar:;~g'."::,LHGRmP

'!i'

:::::::-'.::Eppes'tl're':::.'.-;:>:;:.'::.,"',.".,:,"'.:.':.,:":.',":f imit";-.t:,"'.

0.0 10.7.1 7.0 11;78 35;0 10.65 0.2 10.75 8.0 11.95 r42 13 9.36 1:0 10.86 9.0 12.09 2.0 11.01 10.0 12.20 3.0 11.19 12.5 12.37 4.0 11.35 15.0 12.47 5.0 11.47 20.0 12.37 6.0 11.62, 25.0 11.77

.0 TVANuclear Fuel TVA-COLR-BF2C10 Core Operating Limits Report Revision 0, Page 18 Figure 9 Power DeyentIent MAPLHGR Factor - MAPFAC(P) 1.2 0.8 < 50% Coro Flow O

+os 0.4 I

I I

>> 50% Core Row

-0.2 I

I I

I I

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

MAPLHGR(P) = MAPFAC(P) x MAPLHGRstd.

For For 25% > P:

MAPLHGRstd = Standard MAPLHGR Limits 25% < P < 30%:

NO THERMALLIMITS MONITORING REQUIRED MAPFAC(P) =0.60+ 0.005(P40%) For < 50% CORE FLOW

MAPFAC(P) = 0.46+ 0.005(P-30%) For > 50% CORE FLOW For 30% < P  : MAPFAC(P) = 1.0 + 0.005224(P-100%)

These values bound both Turbine Bypass InService and Out<fervice

0 4l TVANuclear Fuel TVA-COLR-BF2C10 Core Operating Limits Rcport Revision 0, Page 19 Figure 10 Flow. Dependent. MAPLHGR Factor - MAPFAC(F)

MAX FLOW < 102.5%

0.9 0.8 O

M..0.7 MAXFLOW ~ 1071L 0.6 0.5 0.4 30 60 70 80 Core Flow ('/i Rated)

MAPLHGR(F) = MAPFAC(F) x MAPLHGRstd MAPLHGRstd = Standard MAPLHGR Limits MAPFAC(F) = MINIMUM(1.0,Af

• Wc /100+ Bf)

Wc =% Rated Core Flow Af'and Bf are Constants Given Below:

102.5 0.6784 0.4861 107.0 0.6758 0.4574 These values bound both Turbine Bypass In<ervice and Out<service.

The 102.'5% maximum flow line is used for operation up to 100% rated flow.

The 107% maximum flow line is used for operation up to 105% rated flow (ICF).

II 0 TVANuclear Fuel t

Core Operating Limits Report TVA-COLR-BF2C10 Revision 0, Page 20 Figure 11

. MCPR Operating Limit for GE13 1.42 1.41 Pl 1.4 Turbin e Bypass 0 ut&f<ervice O

o 1.39

.N 1.38 g 1.37 Turbine Bypass In<ervlce

< 1.38 C.

O 1.35 1.34 1.33 0 0.1 0.2 0.3 0.4 0.5 0.6 0.7 0.8 0.9 1 Option A Option B Tau (z)

.:,",,Exjios'ice,';Rartge".:i .;,"'..",.!OQt-'.Of'dijfci""..<:, ".,':"$:;Option.A-.:;."';:: g~;.:;:0'ptfciti::B'gg!

BOC10 to EOC10 na 1.37 1 1.34 BOC10 to EOC10 Turbine B ass 1.41 1.38 Notes

1. Use this value at BOC10 prior to performing scram time testing.

0 4 TVANuclear Fuel TVA-COLR-BF2C10 Core Operating Limits Rcport Revision 0, Page 21 Figure 12 MCPR Operating, Limit for GE11 1.42 ED 1.41 CI

,1.4 O

1.39

.E 1;38 Tu rbine Byp ass Out&service 1.37 1.36 O Turbine Bypass!n Nervlce Z 1.35 1.33 0 0.1 0.2 0.3 0.4 0.5 0.6 0.7 0.8 0.9 10 Option B Option A Tau (q)

,:,gttt&fpeiVIce>,,.'". :;ij:::O'Ation".::A'>'.,.:i.:

+Pzvx~" i; ':i%;:,

.;.:,IKjp'aSttri,::,Range:'5':+gz

+~>OPtiorINB!.',;t.:.,'OC10

'OC10to EOC10 na 1.35 1 1.34 to EOC10 Turbine B ass 1.39 1.36 Notes

1. Use this value at BOC10 prior to performing scram time testing.

0 II TVANuclear Fuel t

Core Operating Limits Report TVA-COLR-BF2C10 Revision 0, Page 22 Figure 13 MCPR Operating Limit for GE9B (GE8X8NB) 1.39

'oC 1.37 O

I 1'.36 urblne Byp ass Outf E

g 1.35 0

rc 1.34 O Turbln e Bypass InService 1.32 0 0.1 0.2 0.3 0.4 0.5 0.6 0.7 0.6 0.9 1 Option B Option A Tan (q)

,'-,,,Ojitiort;A:

g,::;.'.j':,':,pption::BI:':;.,;"':.'"Tits'=...1 0'."-;":" ..- r'",.Ti'ti=;0;Oj":";.:,,',

BOC10 to EOC10 na 1.34 1 1.34 BOC10to EOC10 Turbine B ass 1.36 1.34 Notes

1. Use thh value at BOC10 prior to performing scram time testing.

0 iy TVANuclear Fuel TVA-COLR-BF2C10 Core Operating Limits Report Revision 0, Page 23 Figure 14 MCPR Operating Limit for GE7B (BP8XSR) 1.39 1.38 1.37 O

s 1.36 E

g 1.35 Turbine Bypass In<ervice 8 Outf& ervlce 0 1.34 O

1.32 0 0.1 0.2 ,

0.3 0.4 0.5 0.6 0.7 0.8 0.9 Option B Option A Tau (z)

.;:;Sxp'os'ure;.:Ra'ng'e;,;:;;;: F,".;,iOttt&fpeptice~;;,~

BOC10 to EOC10 na 1.34 1 1.34 BOC10 to EOC10 Turbine B ass 1.34 1.34 Notes

1. Use this value at BOC10 prior to performing scram time testing.

II

-J

F TVANuclear Fuel TVA-COLR-BF2C10 Core Operating Limits Report Revision 0, Page 24 Figure 15 Power Dependent MCPR(P) Limits 3.2 I i50II FLOW(TSOOS) 2.8 CL IO EO 2.6 o cO a.

A 2.4 O.,O

'h oN0 O 0 <<50% FLOW (raoos) 2.2 R O.

g 0 1.8 O

0 0 1.6 1.4 Eg 1.2 0 10 20 30 40 50 60 70 80 90 100 Power (% Rated)

OPERATING'LIMITMCPR P = K 'LMCPR 100 For P < 25%: NO THERMAL LIMITS MONITORING REQUIRED For 25% < P < Pbypass :(Pbypass = 30%)

Kp = [Kbyp+ 0.02(30%-P)]/OLMCPR(100)

Turbine B ass In&ervice Kbyp=1.97 For < 50% CORE FLOW Kbyp = 2.21 For > 50% CORE FLOW Turbine B ass Out-Of&ervice Kbyp = 2.01 For < 50% CORE FLOW Kbyp=3.01 For > 50% CORE FLOW For 30% < P <45%  : Kp = 1.28+ 0.01340(45%-P)

For 45% < P <60%  : Kp = 1.15+ 0.00867(60%-P)

For 60% < P  : Kp = 1.00+ 0.00375(100%-P)

Ik 4l TVANuclear. Fuel TVA-COLR-BF2C10'evision Core Operating Limits Report 0, Page 25 (Final)

Figure 16 Floxv Dependent MCPR Operating Limit - MCPR(F) 1.'6 1.5

.1.4 MAXFLOW < 107'4 MAXFLOW i 102.0~/

1.3 1.2 30 70 core Flow (% Rated)

For Wc < 40%  : MCPR(F) = (Af'Wcl100+ Bf)'[1+0.0032(40-Wc)]

For. Wc > 40%  :. MCPR(F) ~ MAX(1.23, Af'Wcl100+ Bf)

Wc ~% Rated Core Flow Af and Bf are Constants Given Below:

, l",:gaximunt%

,'< Cere',FfoIhr~

!$:::.li:Raated;5'02.5 1.701 107.0  %.603 1.745 These values bound both Turbine Bypass InZervice and Out-OfZervlce.

The 102.5% maximum flow line ls used for operation up to 100% rated, flow.

The 107% maximum flow line ls used for operation up to 105% rated flow (ICF).

il..