ML060620564

Issuance of the Core Operating Limits Report for Reload 10, Cycle 11, Revision 4

ML060620564
Person / Time
Site:	Limerick
Issue date:	03/02/2006
From:	Cowan P Exelon Nuclear
To:	Document Control Desk, Office of Nuclear Reactor Regulation
References
Download: ML060620564 (26)

Text

Exelon Nuclear www.exeloncorp.com 200 Exelon Way Kennett Square, PA 19348 TS 6.9.1.12 March 2,2006 U.S. Nuclear Regulatory Commission Attention: Document Control Desk Washington, DC 20555 Limerick Generating Station, Unit 1 Facility Operating License No. NPF-39 NRC DQ&& No. 50-35.2

Subject:

Issuance of the Core Operating Limits Report For Reload 10, Cycle 11, Revision 4

Dear SirlMadam:

Enclosed is a copy of the Core Operating Limits Report (COLR) for Limerick Generating Station, Unit 1, Reload 10, Cycle 11, Revision 4. Revision 4 of this report incorporates changes associated with the implementation of the PANACl 1 based 3D Monicore core monitoring system.

This COLR is being submitted to the NRC in accordance with LGS, Unit 1 Technical Specifications (TS) Section 6.9.1.1 2.

If you have any questions, please do not hesitate to contact us.

Very truly yours, Director, Licensing and Regulatory Affairs Exelon Generation Company, LLC Enclosure cc: S. J. Collins, Regional Administrator, Region I, USNRC S. Hansell, USNRC Senior Resident Inspector, LGS T. Valentine, Project Manager [LGS], USNRC

Limerick Gnit 1 Cycle 11 COLR COLR Limerick I, Rev. 4 1 Page 1 CORE OPERATIX LIMITS REPORT FOR LIMERICK GENERATING STATIONuNrT 1 RELOAD 10, CYCLE 11 Reviewed By: Dace:

W. P. Gassmann Independent Reviewer Approved By:

Limerick Knit 1 Cycie 11 COLR COLR Limerick 1, Rev. 4 I Page 2 Page I .O Terms and Definitions 5 2.0 References 6 3.0 Cenerai Information 7 4.0 MAJ?LHGR Limits 8 5.0 MCPR Limits 13 6.0 Linear Heat Generation Rate Limits 18 1 7.0 Control Rod Block Setpoints 23 8.0 Turbine Bypass Valve Parameters 24 9.0 Stability Protection Setpoints 25 10.0 Modes of Operation 25

Limerick h i t 1 Cycle 11 COLR COLR Limerick 1, Rev. 4 I Page 3 Page Table 4-1 lZiZdLPLWGR Versus Average Planar Exposure Bundle Type GE13-P9cTB417-13GZ-1WT- 146-7: (GEi 3 ) 9 Table 4-2 MAPLHGR Versus Average Planar Exposure Bundle Type GE13-P9CT'B4 17-1 1GZ- I OOT- 146-T fGE13) 9 Table 4-3 hWLHGR Versus Average Planar Exposure Bundle Type GEI4-PI 0CN~4~7-7G8,O/gG7.0-~~T"l~O-T-2527 (GE14C) 10 Table 4-4 MAPLHGR Versus Average Planar Exposure Bundle Type GEI4-PI0CNAJ341'7-t3GZ-1OOT-150-T-2528 (GE14C) 10 Table 4-5 MAPLHGR Versus Average Planar Exposure Bundle Type G E l 4 - P l ~17-768.01~G7.0-80~45R-

~ ~ 4 150-T-2531 (GE14C) 1 Table 4-6 W L H G R Versus Average Planar Exposure Bundle Type GE14-P10CNAB417-15GZ-IOOT-iSO-T-2592 (GE14C) 11 Table 4-7 MAPLHGR Versus Average Planar Exposure Bundle Type GEl4-PIOCNAB4~14-14GZ-1~-150-T-2701 (GEf4C) 12 Table 4-8 MAPLHGR Single Loop Operation (SLO) Reduction Factor I2 Table 5-1 Operating Limit Minimum Critical Power Ratio 14 Tabk 6-1 Linear Heat Generation Rate Limits 1s Tabte 6-2 LHGR Single Loop Operation (SLO) Reduction Factor 18 1 Table 7-1 Rod Block Monitor Setpoints 23 Table 7-2 Reactor Coolant System Recirculation Flow Upscale Trip 23 Table 8-1 Turbine Bypass System Response Time 24 Table 8-2 ~ i n ~ Required

~ u m Bypass Valves To Maintain System Operability 24 Table 9-1 OPRM PBDA Trip Setpoints 25

Limerick Unit 1 Cycle 11 COLR COLR Limerick 1, Rev. 4 f Page 4 Page Figure 5- 1 Power Dependent:,tlCPR Limit Adjustments and ~ u ~ t ~ p ~ ~ ~ r ~

Figure 5-2 Power Dependent MCPR Limit Adjustments and ~ u l ~ ~ p t-~TBVOQS ers Figure 5-3 Flow Dependent MCPR Limits MCPR(F)

Figure 6-1 Power Dependent LHGR Muttiplier LHGRFAC(P}

Figure 6-2 Power Dependent LHGR Multiplier LHGRFAC(P) - TBVOOS Figure 6-3 Flow Dependent LHGR Multiplier LHGRFACF)

Figure 6-4 Flow Dependent LHGR Muftiplier LHGRFACIF) -SLO

CQLR Limerick I, Rev. 4 f Page 5 ARTS APRM and EU3M Technical Specification Analysis DTSP Rod Biuck Monitor Downscale trip setpoint End of Rated (EOR) The cycle exposure at which reactor power is equal to 3458 MWth with recirculation system flow equal to 100%, all control rods fully withdrawn, all feedwater heating in service and equilibrium Xenon.

FFWTR Final Feedwater Temperature Reduction FWHOOS Feedwater Heaters Out of Service ESP Rod Block Monitor High trip setpoint XCF Increased Core Ffow ESP Rod Btock Monitor htermediate trip setpoint LHGR Linear Heat Generation Rate LTSP Rod Biock Monitor Low trip setpoint kWFAC(F) ARTS MAPLHGR thermal limit flow dependent adjustments and multipliers MAPFAC(P) ARTS MAPLHGR t h e m 1 h i t power dependent adjustments and multipliers MAPLHGR Maximum Average Planar Linear Heat Generation Rate MCPR hilinirnum Critical Power Ratio MCPR(P) ARTS MCPR thermal limit power dependent a d j ~ s ~ m ande n ~niuitipliers

~

MCPR(F) ARTS MCPR thermal limit flow dependent adjustments and multipliers MELLLA Maximum Extended Load Line Limit Analysis OPRM PBDA Oscillation Period Range Monitor Period Based Detection Algorithm RCF Rated Core Flow RPTOOS Recirculation Pump Trip Out of Service SLMCPR Safety Limit Minimum Criticat Power Ratio SLO Singie Loop Operation TBVOOS Turbine Bypass Valves Out of Service

Limerick Unit 1 Cycle 11 COLR COLR Limerick 1, Rev. 4 1 Page 6 2.0 RiBERENCES I. Technical S ~ c i f ~ c a and n s for Limerick genera tin^ Station Unit I, Docket No.20-352,

~ ~ ~Bases License No. NPF-39.

2. ~ S u p p I e r nReioad

~ ~ ~ I Licensing Report for Limerick Generating Station Unit 1. Reload 10 Cycle 1 l, Global Nuclear Fuel Document No. oo00-0018-24I 0-SRLR, Revision 0,January 2004.

3. Lattice Dependent MAPLHGR Report for Limerick Generating Station Wnit 1 Reload 10 Cycle It.

Global Nuclear Fuet Document No. ~ - 0 0 1 8 - ~ 4 1 0 - ~ ~ L H Revision G R , 0, February 2004.

4. Lattice Dependent MAPLHGR Report for Limerick Generating Station Unit 1 Reload 9 Cycle lo, Global Nuclear Fuel Document No. J l l - O 3 9 8 4 W L , Revision 0, January 2002.

5. GEI4Fuel Design CycIe-IndependentAnalyses for Limerick Generating Station Units 1 and 2, GE-NE-L 12-00885-00-0IP, March 200 1.

6. OPL-3 Transient Protection Parameters Verification for Reload Licensing Analyses for Limerick I Reload 10 Cycle I I, Resoived as documented in DRF 201 1 1 (Ll CI 1 Reload Licensing DRF).

7. Limerick Generating Station Units f and 2 ECCS-LOCA Evaluation for CE14, CE Nuclear Energy Document No. CE-Nl?-J11-03793-09-0tP, February 2001.

8. ARTS Flow-Dependent Limits with TBVOOS for Peach Bottom Atomic Power Station and Limerick Generating Station, GEhJ Document NEDC-32847P, June 1998.

9. General Electric Standard Application for Reactor Fuel*, *%DE-24011 $-A- 14, June 2ooO and US.

Supplement NEDE-2401 1-P-A-14-US, June 2000.

10. Power Range Neutron Monitoring System Setpoint Calculations Limerick Generating Station, Units I

&2 Mod. No. wO224, LE-0107, Rev. 0, March 2 W .

1 1 . Fuel Bundfe Information Report for Limerick Generating Station Unit 1 Reload 19 Cycle 1l, CIobai Nucfear Fuel Document No. 0000-00f 5-2410-R3IR,January 2004.

12, defeted

13. Limerick 1 and 2 Off-Rated Anaiyses Below the PLU Power Level,GE Nuclear Document No. GE-

~ - ~ ~ 3 7 ~ 3 2 5 3March - R 02005

.

14. Limerick 1 Cycfe 11 Option III Stability Analysis, GE Nuclear Energy Document Xo. GENE-0000-0033-0728-R0, March 2005.

t

Limerick Unit 1 Cycle f l CULR CQLR Limerick 1, Rev. 4 I Page 7 3.0 GENERAL ~ ~ F O ~ ~ A T I ~ ~

This report provides the f ~ l I o w i ncycfe-

~ cifie parametcr limits for Limerick Generating Station Unit i Cycle 1 f :

0 Maximum Average Planar Linear Heat Generation Rate ( W L H G R )

0 Minimum Critical Power Ratio (MCPR) 0 Singfe Loop Operation (SLO) MCPR adjustment ARTS MCPR thermal limit adjustments and multipliers {MCPR(P) or MCPR(F))

0 ARTS LHGR thermal limit multipfiers ~ ~ ~ ~ or~~ F - ~A ~ ~ ~ ~~ PF )~ ~ ( ~ ) )

0 Rod Black Monitor (mM)setpoints MAPLWGR single loop operation reduction factor e L1CK cingie ioop opcmiott ~~~~~~~~~~~ fmor 0 Linear Heat Generation Rate (LHGR)

Turbine Bypass Valve parameters 0 Reactor Coolant System Recirculation Flow Upscale Trips 0 OPRM. Period Based Detection Algorithm (P3DA) trip setpoints These values have been determined using MC-approved methodoiogy (Reference 9), and are established such that all applicable Iimits of the plant safety analysis are met.

This report is prepared in accordance with TechnicaI Specification 6.9.1.9 of Reference 1. Preparation of this report was performed in accordance wirh Exelon Nuclear, Nuclear Fuel Management T&J?%f NF-AB-I 20-3crcxf. I The data presented in this report is valid for all licensed operating domains on the operating map, including:

0 Maximum Extended Load Line Limit down to 81% of rated core flow during full power operation Increased Core Flow (ICE) up to 1 f 0% of rated core flow Final Feedwater Temperature Reduction (FFWTR) up to 105OF during cycle extension operation Feedwater Heater Out of Service (FWHOOS) up to 60°F feedwater temperature reduction at any time during the cycle prior to cycle extension.

Further information on the cycle specific analyses for Limerick 1 Cycle 1 1 and the associated operating domains discussed above is available in Reference 2.

Limerick Unit 1 Cycle 11 COLR COLR Limerick 1, Rev. 4 1 Page 8 4.Q MAPLZIGR LIMITS HCR limits provided in Tables 4-1 ~ r o u 4-8~ hare referenced in Technical ~ ~ c i f i c a t i o3.2.1, ns The limiting W L H G R value for the most limiting lanice (excluding natural uranium) of each fuel type as a function of average planar exposure is given in Tables 4- I through 4-7 (References 3 and 4). Tables 4-1 through 4-7 lire used when hand calculations are required as specified in Technical Specification 3.2.1. For single loop operation, a reduction factor is used which is shown in Table 4-5(Reference 2).

Limerick Knit 1 Cycle 11 COLR COLR Limerick 1, Rev. 4 It Page 9 Tabie 4-1 MAPLHGR Versus Average Planar Exposure Bundle Type GE13-~TB417-1362-100T-f46-T(GE13)

(Reference 4)

I  ! I 1 1 1 1 Avg. Plan Avg. Plan Avg. Plan Exposure MAPLHGR Exposure MAPLHGR Exposure ~ 1 A ~ L ~ IG R 0.0 10.4% 7 .0 1 1.53 25.o 12.01 0.2 10.54 8.0 f 1.69 30.0 11s9

, 1 I I 1 .o 10.65 9.0 1 I .85 35.0 10.96 2.0 10.79 10.0 i 2.02 1 40.0 10.32 3 .O 10.93 12.5 12.26 45.0 9.66 t I I I I  !

-

1 4.0 f 11.08 I 15.0 1 12.45 I S0.0 1 8.9'7 1 5 '0 11.22 17.5 12.44 55.0 7.43 6.0 11.37 20.0 12.32 I 58.03 6.29 Table 4-2 MAPLHGR Versus Average Planar Exposure Bundle Type GEf3-P9CTB417-11G2-100T-lLt6-T fGE13)

(Reference 4) 1 1.0 1 10.93 1 9.0 1 12.06 1 35.0 1 10.96 I 2.0 11.05 12.21 a.0 10.33 3 .0 1 11.17 f 2.5 I 12.43 45.0 9.67 4.0 11.31 15.0 f 2.55 50.0 8.98 i I f I I

5.0 11.45 17.5 f 2.47 55.0 7.49 j 6.0 I 11.59 20.0 12.32 58.2 6.29

Limerick Unit 1 Cycfe 11 COLR COLR Limerick 1, Rev. 4 1 Page 10 Table 4-3 4.0 10.34 15.0 11.04 50.0 7.87 5.0 10.49 17.0 10.95 55.0 5.89 t I Table 4-4

,WLI-XGR Versus Average Planar Exposure Bundle Type GE14-P1OCNAB417-13GZ-10OT-150-T-2528 (GEL4C)

(Reference 4)

Avg. Pian Avg. Plan Avg. Plan Exposure MAPLHGR Exposure MAPLHGR Exposure MAPLHGR (GWd/ST) (kW/ft) (GWdlST) (kW/ft) (CWdlST) 0.0 10.17 7.0 10.92 25.0 10.34 0.2 10.22 8.0 f 1.02 30.0 1.o I 0.26 9.0 1 f.09 35.0 2.0 10.32 10.0 fl.t.5 40.0 1 3.0 1 10.42 1 12.0 1 11.25 f 45.0 4.0 I0.53 150 I 1.09 50.0 I I I I 5.0 1 10.66 1 17.0 1 20.98 SS.0

[ 6.0 10.81 20.0 10.78 57.12

Limerick Unit 1 Cyde 1I COLR COLR Limerick 1, Rev. 4 I Page 11 Table 4-5

~~L~~~ Versus Average Planar Exposure Bundk Type CJE14-P10CN~417-7G8.0/8G7.0-80~~5R-150-T-2531 (GE14C)

(Reference 4)

M;@LHGR Versus Average Planar Exposure Bundie Type ~~14-P10CNAB417-15GZ-1QOT-fSO-T-2592 (GE14G)

(Reference 3) r i I I I I 1 Avg. Ptan Avg. PIan I Avg. Plan Exposure hiIAPLHCR Exposure MAPLHGR Exposure NIAPLHGR (GWdlST) 1 (kW/ft) {GWdlST) fkW/ft) (GWd/ST) (kW/ft}

0.0 I0.00 8.0 10.91 '0.0 10.76 i

0.2 10.01 9.0 10.99 2s .0 10.34 1.0 i 0.03 10.0 11.07 i 30.0 9.87 5.0 I 10.49 i 14.0 50.0 7.87 1

'

i 6.0 1 10.64 1 15.0 I 11.04 1 55.0 I 5.89 1 7.0 10.81 I 17.0 10.95 57.06 4.86

Limerick Unit 1 Cycle 11 COLR COLR Limerick 1, Rev. 4 I Page 12 Table 4-7 iMAPLWGR Versus Average Planar Exposure Bundle Type ~ ~ 1 4 - ~ 1 U1 4~ ~ ~~ -41 1~ ~~ - -1 5 ~ -(GE14C)

~-2701 (Reference 3)

I I 2.0 10.24 11.0 1I25 35.0 9.24 3.0 10.35 12.0 11.28 40.0 8.72 i I t I 4.0 10.47 13.0 11.21 45.o 8.24 5.0 10.61 14.0 11.14 50.0 7.76 I I 6.0 10.73 15.0 I 1 .ox 55.0 5.86 7.0 10.86 17.0 10.96 57.02 4.85 Table 4-8 W L H G R Single Loop Operation (SLO) Reduction Factor (Reference 2)

Limerick Unit 1 Cycle 11 COLR COLR Limerick 1, Rev. 4 f Page 13 The MCPR values provided in Table 5-1 are referenced in Technical Specification 3.2.3. Table 5-t is derived from the Reference 2 analyses and is valid for at! Cycle i 1 fuel types and operating domains. Table 5-1 includes treatment of these MCPR limits for SLO. Bounding MCPR values are also provided for inoperable Recirculation Pump Trip or inoperable Steam Bypass System. These two options represent the Equipment Out of Service conditions. The cycle exposure, which represents EOR, is given in the latest verified and approved Cycle Management Report or associated Engineering Change Request.

ARTS provides for power- and flow-dependent thermal limit adjustments and muftipliers, which allow fox a more reliable administration of the MCPR thermal limit. The tlow-dependent adjustment MCPR(F) is sufficiently generic to apply to ail fuel types and operating domains (References 2 and 8). In addition, there are also two sets of p o w ~ r - d e ~ ~ dMCPR e i ~ t multipliers for use with the Turbine Bypass Valves in service and TBVOOS conditions (Reference 13). Section 8.0 contains the conditions for Turbine Bypass Valve Operability. These adjustments and muhipliers are shown in Figures 5-1 through 5-3 and are referred to by Technical Specification 3.2.3. The MCPR(P) curves are independent of recirculation pump trip operability (Reference 13).

Limerick Unit 1 Cycle 11 COLR COLR Limerick 1, Rev. 4 I Page 14 Operating Limit ~ n i Critical m Ratio (OLninCPR)

~ ~ Power (References2 and 5)

TBV In Service and TBV out of Service RPT Out of Service RPT In Service (TBVCtoS) (RPTOOS) 1.33 I 1.36 1.38 I 1.41 EOR- 2000 1.38 1 1.41 t .43 I .46 I. 4 P f .433 1.4 1.47 I. When Tau does not equal 0 or 1, determine OLLVCPRvia linear interpolation.

2. OLMCPR limit set by the Single Loop Operation Recirculation Pump Seizure Analysis (Reference 2.)

3. This tabie is vatid for all Cycle I 1 fuel types.

Limerick Unit 1 Cycle I1 COLR COLR Limerick 1, Rev. 4 I Page 15 FIGURE 5-1 Power Dependent MCPR Limit Adjustments And Multipliers This Figure Is Valid For At1 Operating Domains except TBVOOS (References2 and 13) 4.0 3.8 3.6 3.4

@ 3.2 3

3 2 3 . 0

-

2 2a 2 . 8 2.67 u

2.6

?

1*

I.

2.1 2.2

-c 60% Flow 2.45 3

3M 2 . 0

$ 1.8 2

1.6  : 1.481 1 . 4 1.3 1.2 1 . 0 0 2 0 40 60 80 100 Power(% Rated)

L,imerick Unit 1 Cycle 11 COLR COLR Limerick 1, Rev. 4 I Page 16

-

Power Dependent MCPR Limit Adjustments And Multipliers TBVOOS This Figure 1s Valid For The TBVOOS Operating Domain (References 2 and 13) 5.0 4.6 4.2

,. .-

g 3.8 0

2 9

E3-4 9

? 3.0

$

6

>\  :. .* 2.64

&

-

J 2.6

-< 60%

42 E 2.2 3

1.8 1.4 1.0 0 20 40 60 80 iao mwer (% Rated)

Limerick Unit 1 Cycle If COLR COLK Limerick 1, Rev. 4 1 Page 17 FIGURE 5-3 Flow Dependent iLICPR Limits MCPR(F)

This Figure Is Valid For All Operating Domains (References 2 and 8) 2.00 1.90 MCPR(F) = The Maximum of EI-FWER 1.25 OR { -0.5784x (wT/lW) + 1.7073) 1.80 JvT = 76 Rated Core Flow 2 - 7 0 n 1.60 tia.

0 z 1.50 1.40 1.30 2.20 1.10 30 40 50 60 7 0 80 90 100 1x0 C o r e Flow (a Rated)

Limerick Unit 1 Cycle t l COLR COLR Limerick 1, Rev. 4 I Page 8 The ma~imumLHGR value for each fuel type for use in Technical Specification 3.2.4 is given in Table 6-1 below. The LHGR is an exposure dependent vatue. Due to the proprietary nature of these values only the maximum LHGR for each fuef type is listed in Table 6- t .

ARTS provides for power- and flow"dep~~ident thermal limit multipliers, which allow for a more reliable ad~inis~ration of the LHGR thermal limits. There are two sets of flow-dependent LGHR multipliers for duaf-loop and single-loop operation (References 2,s and 8). In addition, there are also two sets of power-dependent LHGR multipliers for use with the Turbine Bypass Valves in service and TBVOOS conditions (Reference 13). Section 8.0 contains the conditions for Turbine Bypass Valve Operability. The LHGR e r sshown in Figures 6-1 through 6 3 and are referred to by Technical Specification 3.2.4.

m u ~ ~ i p l ~are Thermal limit monitoring must be performed with the more limiting LHGR limit resulting from the power-and flow-biased calculation. The LHGRFAQP) curves are independent of recirculation pump trip operabitity (Reference 13). For single loop operation, a reduction factor is used which is shown in Table 6-2 (Reference 2).

TABLE 6-1 Linear Heat Generation Rate Limits (Reference 11)

FUEL TYPE MAXIkfVM VALUE GE13 14.4 kW/ft GEI4 13.4 kW/ft Table 6-2 LHGR Single Loop Operation (SLO) Reduction Factor (Reference 2)

SLO reduction factor 0.79

Limerick Unit 1 Cycle 11 COLR This Figure Is Valid For the All Operating Domains except TBVOOS)

(Reference 13) 1.0 a.8

&

u

.E 2 0.6 8

L;z c!i LHGR(P) = LHGRFACIP)

• LHGRstd g

FOR P c 25% . NO THERMAL LIMIT MOPUITORING 55 0.4 REQU ERED Y NO ttMITS SPECIRED

E FOR 25% S; P < 30%

LNCRFAC(P)= 0.490 i0.0010(P-30)

For i 60% Row 2 0.2 a I ,

t LNGRFACfP) = 0 473 i0 007%P-30) t .

• I For > 60% Now FOR 30% s P . LHGRFAC(P) = 1 .0 i0.005224(P- 100) 0 . 0 60 60 100 Potrr?r(%Rated)

Limerick Unit 1 Cycle 11 COLR COLR Limerick 1, Rev. 4 Page 20 FIGURE 6-2 Power Dependent LHGR ~ ~ u ~ LHG ~ i ~ l i ~ r This Figure Is Valid For The TBVOOS Operating Domain (Reference 13)

~- ~- __

LHGRfP) = LHGRFACIR

• LHGRstd FOR P c 25% FjO THERMAL L&lIT \lOrLKORlNG

. . REQLrRED CO LIMITS SPECIRED FOR 25°C 2 P < 30% LHGRF4C(P) = 0 $90 + 0 00$.1(P-70)

For 5 609 Row LtfGRFAC(P)= 0 386 i 0 NkX(P-10)

For > 40% Row FOR 30% 5 P < 509 LHCRFAC(PI = 0 939 + 0 0052?.t(P- 100)

FOR P ? 50% LHGRFAC(P) = 1 0 + 0 005224 P- 100)

'. ..

0 a0 60 60 80 100 Power (Or, Rated)

Limerick Unit 3 Cycle 11 COLR COLR Limerick 1, Rev. 4 Page 21 This Figure Is Valid For All Operating Domains Excluding Single Loop Operation (ReferencesS and 8) 1.1 1.0 0.9

%

5 0.8 9ii ti 9

3 0.7 z

U LHGR(F)= LHGWAC(F)

• LHGRstd 3 FOR Tuo Loop Operation, > 70% WT LHGRFAC(F) = The Minimum of EITHER 1 .O 0.6 OR f 0.0268 x [WT-70)/10+0.97321 FOR Two Loop Operation, 5 70% WT LHGRF;AC(F) = (0.6682 x WT/100)+0.5055 0.5 Where WT = % Rated Core Flow 5.4 30 45 50 60 70 80 90 100 110 Core Flow (a Rated)

Limerick Unit 1 Cyck 11 COLR COLR Limerick 1, Rev. 4 I Page 22 This Figure is Valid For Single h p Operation (Refereaces 2 and 8)

" ._."

.._, .

^^ " ...._,.,.,x.

I LHGR(F)= LHGRFAC(F) LHGRstd FOR Single Loop Operation, LHGRFAC!F! = The Minimum of EITHER 0.79 OR 0.6682 x ~ W ~ / I ~ ~ ~ . ~ ~ S S Where WT = 5% Rated Core Flow 30 40 50 60 7a 84 90 ioa 110 Core H o w (% Rated)

Limerick Unit 1 Cycle 11 COLR COLR Limerick I, ~ e v4. 1 Page 23 7.0 CONTROL ROD BLOCK SETPOINTS Technicaf Specification Limiting Condition for Uperation 3.3.6 requires control rod block i n ~ t r ~ r n ~ n ~ ~ i o n channels shaiil be OPERABLE with their trip setpoints consistent with the values shown in the Trip Setpoint column of Technical Specification Table 3.3.6-2. The Reactor Coolant System Recirculation Flow Upscale Trip is a cycte-specific value and as such is found in Table 7-2 of this COLR. Table 7-2 fists the Nominal Trip Setpoint and Allowable Vatue. These setpoints are set high enough to allow full utifizatton of the enhanced ICF domain up to 1 IO% of rated core flow. Additionatly, the ARTS Rod Block Monitor provides for power-dependent RBM trips. The trip S ~ t ~ i n t ~ a I ~ o wvafues a b l e and applicable RBM signal filter time constant data are shown in Table 7-1 These vafues are for use with Technical Specification 3.3.6.

I TABLE 7-1 Rod Block AhfanitorSetpoints (References2 and 10)

I i LTSP' Nominal Trip Setpoint 12i.5%

Allowabk Value 121.5%

1 ESP' 116.5% 116.5%

t I I I

DTSP' 92.0% 89.0%

1. These setpoints (with Rod Block Monitor filter time constant between 0.1 seconds and 0.55 seconds) are based on a cycte-specific rated RWE MCPR h i t which is less than or equal to the minimum cycle OL&fCPR (see COIR references 2 and 10).

TABLE 7-2 Reactor Coolant System Recirculation Flow Upscale Trip (Reference 10)

I I 1 Nominal Trip Setpoint Il3.456 Allowable Value 115.6%

Limerick Unit 1 Cycle 11 COLR COLR Limerick I, Rev. 4 I Page 24 8.0 TtrRBHE BYPASS VALVE ~ ~ R ~ T E R S The operability requirements for the steam bypass system for use in Technical Specifications 3.7.8 and 4.7.8.C are found in Tables 8-1 and 8-2. If these requirements cannot be met, the MCPR, MCPR(P) and MAPFAC(PJ limits for inoperable Steam Bypass System, known as Turbine Bypass Valve Out Of Service, must be used.

TABLE 8-1 Turbine Bypass System Response Time (Reference 6)

Maximum delay time before start of bypass valve opening following generation of the turbine bypass valve Row signal 0.11 sec Maximum time after generation of a turbine bypass valve ffow signal for bypass valve position to reach 80% of fufl Row 0.3f sec (includes the above delav time)

Reactor Power No. of Valves in Service P 225% 7

Limerick Unit 1 Cycle 11 COLR 9.0 STABILITY PROTECTION SETPQINTS The Limerick 1 Cycle 1 1 Oscillation Poaer Range Monitor (OPRZ.ul)Period Based Detection A~gori~hm (PBDA} Trip Setpoints for the OPRM System for use in Technical Specification 2.2.1 are found in Table 9-t .

These vaIues are based on the cycle specific analysis documented in Reference 13.

Any change to the OLMCPR value andlor ARTS-based power dependent MCPR limits shouid be evaluated for potential impact on the OPRTvf PBDA Trip Setpoints.

T X 9-1 OPRM PBDA Trip Setpoints Corresponding Maximum PBDA Trip Amplitude Confirmation Count Trip Setpoint 10.0 MODES OF OPERATION Limerick Generating Station has been analyzed to operate with a number of operational flexibility features, including increased Core Ftow, Maximum Extended Load Line Limit, Coastdown, EOC Recirculation Pump Trip and Option A/B MCPR Limits. Limerick Generating Station has also been analyzed to operate with a number of equipment out-of-service conditions, inctuding Turbine Bypass Valves 00%Single Loop Operation, Feedwater Heating OOS, Final Feedwater Temperature Reduction and Safety/Relief Valves 00s (up to 2 of 14 safetyhelief valves 00s). Operation is allowed in any combination of these operational flexibility features and equipment out-of-service conditions, with one EXCEPTION, which is that Limerick may NOT aperate with EOC-RecirculationPump Trip out-of-service in conjunction with Turbine Bypass Valves 0 0 s .