ML18137A204: Difference between revisions

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#REDIRECT [[U-604424, Submittal of the Core Operating Limits Report for Clinton Power Station, Unit 1, Cycle 19, Revision 13]]
| number = ML18137A204
| issue date = 05/15/2018
| title = Submittal of the Core Operating Limits Report for Clinton Power Station, Unit 1, Cycle 19, Revision 13
| author name = Stoner T
| author affiliation = Exelon Generation Co, LLC
| addressee name =
| addressee affiliation = NRC/Document Control Desk, NRC/NRR
| docket = 05000461
| license number = NPF-062
| contact person =
| case reference number = U-604424
| document type = Fuel Cycle Reload Report, Letter
| page count = 28
}}
 
=Text=
{{#Wiki_filter:Clinton Pm.,,er Statioo 8401 Power Road Clinton, ll 61727 U-604424 May 15, 2018 U. S. Nuclear Regulatory Commission Attention:
Document Control Desk Washington, D.C. 20555-0001 Clinton Power Station, Unit 1 Facility Operating License No. NPF-62 NRG Docket No. 50-461 ~7 Exelon Generation
 
==Subject:==
Submittal of the Core Operating Limits Report for Clinton Power Station, Unit 1, Cycle 19, Revision 13 In accordance with Technical Specification 5.6.5, Core Operating Limits Report (COLR), Item d., Exelon Generation Company (EGG), LLC is submitting Revision 13 of the COLR for Clinton Power Station, Unit 1, Cycle 19. There are no regulatory commitments contained in this letter. Should you have any questions concerning this report, please contact Mr. Dale Shelton at (217) 937-2800.
Respectfully, Theodore R. Stoner Site Vice President Clinton Power Station GS/lam
 
==Attachment:==
 
Core Operating Limits Report for Clinton Power Station Unit 1, Cycle 19, Revision 13 cc: NRG Regional Administrator, Region Ill NRC Senior Resident Inspector
-Clinton Power Station ATTACHMENT Core Operating Limits Report for Clinton Power Station Unit 1, Cycle 19 Revision 13 Exelon Nuclear* Nuclear Fuels CL1C19 Core Operating Limits Report DOC ID: COLR Clinton 1 Rev. 13 Prepared By: Reviewed By: Reviewed By: Reviewed By: Approved By: CORE OPERA TING LIMITS REPORT FOR CLINTON POWER STATION UNIT 1 CYCLE 19 .. Date: 4120/2018 G2-aJL I _sJ Date: 1;/~a/l 8 eugel Date: 4/20/2018
~L71;~ Independent Reviewer -Kevin Smith Date:. '-/ t._2..o/1g_
N~~hnson Date: 23APR18 Date: ~-:1.;--tp Page 1 of 26 Exe1onRuclear-Nuclear Fuels CL1C19 CoreOperating Limits Report Revision History Ust of Tables 1.0 Terms and Definitions 2.0 General Information 3.0 MAPLHGR Limits 4.0 MCPR Limits Table of Contents 5.0 Linear Heat Generation Rate Limits 6.0 Reactor Protection System {RPS) Instrumentation 7.0 Turbine Bypass System Parameters 8.0 Stability Protection Setpoints 9.0 Modes of Operation 10.0 Methodology 11.0 References
'Page2of26 DOCID:COI.Rcnnton 1 Rn.13 3 4 6 8 9 11 17 23 23 24 25 26 26 
&e1on Nudear-NuclearFuels Cl.1Cl9Cone0per.mn.o linffls Report Revision Rev. 13 oocm:: COIRCmiton 1 Rev.13 Revision History Description Rrst issuance for Cycle 19 Page 3 of 26 r &e1anNudear-NmlearFue1s Cl..1Cl9CoJe0J)elillin_glimilsRepmt UstofTah1es DOCRCOl.R.Clinton 1 Re.v.13 Pa§e Table3-1 MAPl.HGRVeisusAverapAanar~
9 Table3..2 MAA.HGR Sin9)e I.mp Operation (Sl0) Multiplier 10 Table 3-3 MAffHGR Mulfiplierfor Loss of "FUll.:" Feedwater Heating 10 Tab1a4-1 Operating Limit Minimum Ctffica1 Power Ratio 12 Table4-2 Power Dependent MCPR Limits MCPR{P) and~ K{P) 13 for Base Case and Two or More lBVOOS TabJe4-3 Power Dependent MCPR Limits MCPR{P) and Mu1fip2iels K{P) 14 for PROOS/PLUOOS Tab1e4-4 DuaJ loop Operation (DLO) Row Dependent MCPR Limits MCPR(F) 15 for Base Case or PROOSJPWOOS Table 4-5 Single Loop Operation (SLO) Row Dependent MCPR Limits MCPR(F) 15 for Base Case or PROOS/PLUOOS Table 4-6 Dual Loop Operation (DLO) Flow Dependent MCPR Limits MCPR(F) 16 for Two or More TBVOOS Table 4-7 Single Loop Operation (SLO) Flow Dependent MCPR Limits MCPR(F) 16 for Two or More TBVOOS Table 5-1 Linear Heat Generation Rate Limits for U~ Rods 18 Table 5-2 Linear Heat Generation Rate Limits for Gad Rods 18 Table 5-3 LHGR Single Loop Operation
{SLO) Multiplier 18 Table 5-4 Power Dependent LHGR Multipliers LHGRFAC{P) 19 Table 5-5 Flow Dependent LHGR Multipliers LHGRFAC{F) for Base Case or PROOS/PLUOOS 20 Table 5-6 Flow Dependent LHGR Multipliers LHGRFAC{F) for Two or More TBVOOS 20 Page4of26 r &e1mJ Nuclear-llucJearFaeJs Cl.1C19Cme0peratingl.imils Report DOCiD:COl.Rainmn 1 Retr.13 Tab1e 5-7 Power Dependent UiGR Mll'ffiplims I.HGRFAC{P) (Loss of"RJU..." 21 Feem.vater Heatin.9}
Tab1e 5-8 Aow Dependent l.HGR Muffip1iem UiGRFAC{f}
for Base Caseor 22 PROOSIPLUOOS (Loss of "RJLl' Feedwater Healing) Table 5-9 Aow Dependent LHGR Mulfipfiers LHGRFAC{f) fur Two or Mme TBVOOS 22 (Loss of "FULL" Feedwater Heating) Tab1e 7-1 Reactor Power Limitation
-Tmbine Bypass Valves Out of Seroice 23 Tab1e 8-1 OPRM PBDA Trip Setpoint 24 Table 9-1 Modes of Operation 25 Page 5 of26 r &e1mJ liudear-ftudearF.uels Cl.1Cf9Cme0peratm,g Umilsftepr,Jt 1..0 Tems and OeliniliDBS BaseCase Coastdown A case analyzed vi1th two {2} Safely-Relief Valves ~(OOS). one (1) Tuibine Contm'J Valve sluck dosed. one (1) Twbine Slop Valvesmck dosed. one (1) Twbine Bypass Valve oos. and up to a 5D"F feedwatertempmalwe reducliOD (FWIR mdudes feedwaler bea'terOOS orfina1 feedwalertempmalure reduclirm) at any point in the cyde operation in Dual Loop mode (RefeRmoe 12). The reactor condition where themml power gradually decreases due to Jue1 depJetion while the fo11owmg conditions are met 1) a1J operable amtro1 rods me fully withdrawn and 2) a1I cycle extens1on techniques have been exhausted includiR9 FFWTR and ICE Design NORMAL Nominal operating temperature for Cfmton is 430°F at rated power. Temperature DLO EOOS FWTR FFWTR FWHOOS ICF LCO LHGR LHGRFAC(F)
LHGRFAC(P)
Loss of 'FULL' Feedwater Heating MAPLHGR MCPR MCPR(F) Dual Reactor Recirculation Loop Operation Equipment Out of Service Feedwater Temperature Reduction, Including FFWTR or feedwater heater OOS Final Feedwater Temperature Reduction Feedwater Heaters Out of Service Increased Core Row Limiting Condition of Operation Linear Heat Generation Rate LHGR thermal limit flow dependent multipliers LHGR thermal limit power dependent multipliers
'FULL' Feedwater heating is temperature witnin :t10 °F of design NORMAL temperature.
The Loss of 'FULL' Feedwater Heating constitutes a change in temperature greater than 10 °F, but less than or equal to 50 °F FWTR. This condition accounts for effects of Asymmetric Feedwater Temperature Operation or AFTO. Maximum Average Planar Linear Heat Generation Rate Minimum Critical Power Ratio MCPR thermal limit flow dependent adjustments and multipliers Page6of26 Exelon Nuclear-Nuc1earFue1s C:UC19Com0pe.rcdin,g Umi!s Repo:rt DOCID:COLRCfud:on 1 ReY_ 13 f\JJCPR{P}
MEU.lA MSIV OLMCPR oos OPRM PBDA PLUOOS PROOS SLO SRVOOS TBVOOS TBSOOS TCV TSV MCPR thermal mmt power depemiemadjllstmems and muffipliB1S Maximum Extended load l.iRe Limit Analysis Main Steam lsolafion Vab.re Operating Limit M'"mimum Cfffica1 Pmver Rafio Out of Senrice Oscillation Power Range Monitor Period Based Detection AJgomhm Power Load Unbalance Out of Service Pressure Regulator Out of Service Single Reactor Recirculation Loop Operation Safety Relief Valve Out of Service Turbine Bypass Valve(s) Out of Service -valves are not crecflled for fast opening or for normal pressure control Turbine Bypass System Out of Service Turbine Control Valve Turbine Stop Valve Page7 of 26 Em1on INm:lJear-NudearFmns Q.1Cl9CmeOJ,mafin,gl.imilsRepmt 2JJ Geneiallnfo~on OOCID:a:nRaintml 1 aa,_ 13 This repmt is prepa1BI m accoJdimce vmh Tedmica1 Specffica1ion 5.6..5 of RefereBce 1_ Power and fiow' depeBdent limils ami mulliplieJS are listed for various power and flow levels. linear mlerpolatitm is to be used to find iRtemmdiate values. lhese va1ues have been deteJmb1ed usiR.g NRC-approved meffmtlolmgies p.resented in Section 10 and are esmblis'hed such that a11 app1icab1e limits of the p1ant safety analysis are met The data presenmd in lhis repoit is valid for all licensed operating domains on the operafin,g map, induding:
* Maximum Extended load Line Limit down to 99% of rated core flow duJin.g fu1J power operation
* Increased Core Flow (ICF) up to 107°.k of rated core flow
* Fma1 Feedwater Temperature Reduction (FFWTR) up to 50°F during cycle extension operation
* Feedwater Heater Out of ServJce {FWHOOS) up to 50°F feedwater temperature reduction at anytime during the cycle prior to cycle extension.
Equipment out of senrioe conditions are as defined in Section 1 and Section 9. Pages of 26 
&e1DD Nuc1ear-NudearFDe1s CUCt9Com()percdnml.imilsRejJDJt 3.0 MAPLHGRUmils 3.1 Tedmical Specmcalicm
 
==Reference:==
 
Sectimas 32.1 aml 3.4.1. 32 Descripfion:
DOCIID.: COlRCJintml 1 Rw. 13 Tab1e 3-1 is used to delemlinelhemaximum average pJanar liJlearheatgeaeramm rate(MAR.HGR) limit. Limls listed in Table 3-1 aie fordua'l reactor JeCiJCu1afion loop operation (OLO). Forsin,gle mactor recin:ula1ion loop operation (SlO). the MAPlHGR limits given in Tab!e 3-1 must be muffiplied bya Sl.O MAPlHGR mulliplier provided in Table 3-2. For loss of "fUU." Feedwaler Heating (a change in temperalure greater than 10 °F. but less than or equal to 50 °F FWTR). lhe MAPlHGR limits given in Table 3-1 must be mu1liplied by a MAPLHGR multiplier provided in Tab1e 3-3. This mullipJier accounts for potentia1 feedwaler riser flow asymmetries (Reference 7). Table3-1 MAPLHGR Versus Average Planar Exposure 1 {Reference
: 3) Avg. Planar Exposure MAPLHGR Limit (GWdfST) (kW/ft) 0.00 13.78 17.15 13.78 60.78 6.87 63.50 5.50 .. 1 Linear interpolation should be used for points not listed in the table. Page 9 of 26 Exelon Nudear-NuclearFuels Q..1Cl9CmeOpemlm9UmilsRepml Tah1e3-2 MAR.HGRSm.g]eloopOpsr..ffion (SLO) Mu1lip1ie1'
~3) Fuel Type GNF2 Tablel-3 0 Mu11ip1ier 0..760 MAPLHGR Multiplier for Loss of "FULL* Feedwater Heating (Reference
: 7) I Fuel Type GNF2 1~1 Page 10 of26 
&e1on Nw::iear-liudearFue1s Q.1C19CmeOperafln.gUmilsRepmt 4..0 MCPR Limits 4_ 1 Technical Specmcalion
 
==Reference:==
 
Sections 3.22. 3..4.1. and 3.7_6_ 42 Desaiplion:
DOCIID:COIBCfirdlm 1 Rmr.13 The Operatin_g Limit MCPR (OLMCPR) is determined from eilher Section 4.2.1 or 4.22,, whichever is greater at any given power and flow condition.
4.2.1 Power--Dependent MCPR For operation less than or equal to 33.3% core thennal power, the MCPR(P) as a function of core thennal power is delermined from Table 4-2 or Table 4-3 depending on p!ant conditions.
For operation at greater than 33.3% core thennal power. the OLMCPR as a function of core thermal power is determined by multiplying the applicable rated condition 01..MCPR limit shown in Table 4-1 by the applicable MCPR multiplier K{P) given in Table 4-2 or Table 4-3. 4.22 Flow-Dependent MCPR Tables 44 through 4-7 give the MCPR(F) as a function of flow based on the appficable plant concfltion.
The limits for dual loop operation are listed in Tables 44 and 4-6. The limits for single loop operation are listed in Tables 4-5 and 4-7. The MCPR{F) delennined from these tables is the flow dependent OLMCPR 4.2.3 Option A and Option B Option A and Option B refer to use of scram speeds for establishing MCPR operating limits. Option A scram speed is the BWR/6 Technical Specification scram speed. The Technical Specification scram speeds must be met to utilize the Option A MCPR limits. Cycle-specific reload analyses performed by GNF for Option A MCPR limits utilized a 20% core average
* insertion time of 0.516 seconds (Reference 6). To utilize the MCPR limits for the Option B scram speed, the cycle average scram insertion time for 20% insertion must satisfy equation 2 in Reference 5 Section 4. If the cycle average scram insertion time does not meet the Option B criteria, the appropriate MCPR value may be determined from a linear interpolation between the Option A and B limits as specified by equation 4 in Reference 5 Section 4. 4.2.4 Recirculation Flow Control Valve Settings The cycle was analyzed with a maximum core flow runout of 109%; therefore, the recirculation flow control valve must be set to maintain core flow less than 109% (92.105 Mlb/hr) for all runout events (References 3 and 12). Page 11 of 26 
&e1on Nndear-!Nm:learFuels CL1C29Com0pe,dn11 UmilsRepmt Tahle4-1 DOCID.:COl.RCfinhm1 Rev.13 Opeiatins limitUinimumCJifical PawerRatio (Rele1em:e3) . EOOS OplionA Option& Combination AU Exposures AU Exposures Base Case DLO 1_,40 1_30 Base case SL.0 1 1-43 1-33 PROOSIPlUOOS 1_44 1_44 DLO PROOSIPWOOS 1_47 1_47 Sl0 1 TwoorMore 1-47 1_37 TBVOOSDLO TwoorMore 1_50 . 1_40 TBV00SSL0 1 Notes for Table 4-1: 1. SLO Option A(B) OLMCPR is the transient DLO Option A(B) OLMCPR plus 0.03 {Reference 3). Page 12 of 26 
&e1an INudear-NudeaTFue1s Cl.1Cl9Cme0pemfin,g limilsRepml DOC*ID:001.Ramtrm 1 Rev.13 T.ab1e4-2 PowerD&pendentMCPR l.imils lMCPR{P)and Uu1fip1ieJs K{P}forBaseCaseand Two or Mom TSV0~2 {RefelB)ce3}
EOOS Com Cme1beJma1 Power(%) Combination Row(% OJ) 21.6 :533.3 >33.3 ~.3 <70..0 >74.0 1DDJ) 111* -MCPR{PJ IKfP) BaseCase <50 2.34 2.34 2.10 oi.o 1.617 1.59D 1.313 1.212 1.163 1.000 OplionAfB
~50 2.48 2.48 225 <50 2.:,/ 2.37
* 2.13 Base Case SLCl 1.617 1.590 1.313 1.212 1.163 1.000 OptionA/B
~50 2.51 2.51 2.2B .. TwoorMore
<50 2.34 2.34 2.10 TBVOOSDLO 1.617 1.590 1.329 1.212 1.163 1.00D OptionAfB
~50 2.48 2.48 2.25 TwoorMore
<50 2.:,/ 2.37
* 2.13 TBVOOSSLO 1.617 1.590 1.329 1.212 1.163 1.000 Option NB ~50 2.51 2.51 2.28 Notes for Table 4-2: 1. Linear interpolation should be used for points not listed in the table. 2. Allowable EOOS conditions are listed in Section 9.0. Page13 of 26 
&e1onfl1Dclear-/NudearF.ue1s Ol..1ct9CmeOprmaiD,gUmilsRepmt DOClll: COl.RClilitml 1 Rew. G Table43 P.owarDepemleDtllJCPR~
MCPR{PJand flht1tiplieJs K(PjfmP.RODSfPWODS~
2 (Rda:atm:3J Com Com Thenna'I Power(%) EOOS Raw(% o.e 21J; SU. >33.3 Combinalian ofRated) . MCPR{P) PRODSIPWOOS
<50 2.34 2.34 210 mo 1.617 OplionAfB
;1!50 2..48 2..48 2..25 PROOSfPWOOS
<50 2Z1 2-Y 2..13 Sl..O 1-617 OplionA/B
;i! 50 2..51 2..51 2.28 . " Noles forTable4-3:
: 1. Linear interpolation should be used for points not listed in the table. 2-Allowable EOOS conditions are risted in Section 9.0. Page14of26 43.3 6D <85A) $A). K{P) . 1.59D 1_43& 1_309 UBI 1_590 1A36 1_309 1_090 1DILO 1..000 1_000 
&e1on Nudear-1NudearFue1s CL1ct9ComOpemfiuJi UmilsRepmt Tahle44 DDa1 Loop Ope:r:ation (DLO) Flow DependentMCPR Umils MCPR{F)forBaseCaseorPROOSrPLUOOS" (Referem:e3}
Coreflow MCPR(F) rA>>rated)
.*o_o 1_88 25_0. 1-70 84_1
* 1.21 109..0 1.27 TabJe4-5 Single Loop Operation (SLO) Flow Dependent MCPR Limits MCPR(F) for Base Case or PROOSIPWDOS 1 (Reference
: 3) Core flow MCPR(F) (% rated) ) *. 0.0 1.91 25;0 1.73 84.1 1.30 109.0 1~30 1 Linear interpolation should be used for points not listed in the table. Page 15 of 26 
~lmdear-Nudearliue1s a.1C19CmeOJ,era1insUmltsRepmt Table445 DDa1 LoopOpmafiDD (DLO) RowDependentlllCPRUmils fillCPR{Fjfm'TwoorMme 1BVODS 11 (Re1elerme3)
CoR!Raw iMCPR{F) (%rated) 0.0 2.04 2.5..0 1.115. 100.0 127 109.0 1.27 Table4-7 Single Loop Operation (SLO) Flow Dependent MCPR Limits MCPR(F) for Two or More TBVOOS 1 (Reference
: 3) Com flow MCPR(FJ (%rated) 0.0 2.07 25.0 1.88 100.0 1.30 109.0 1.30 1 Linear interpolation should be used for points not listed in the table. Page 16 of26 ExekmNudear-NudearFue1s CL.1C19CmeOpeJatingUmilsRepml 5.0 LmearHeatGenmafion Rate Umifs 5_ 1 Technical Spedlicalion
 
==Reference:==
 
Sedion 32.3, 3-4.1. and 3.7_5. 52 Desaiption:
The linear heal generation rate (UiGR) limit is the product of the exposure dependelJI UIGR limit (from Table 5-1 for U02 fue1 rods and Table 5-2 forGadolinia fue1 rods) and the minimum ot. the power dependent lHGR Mulfiplier, LHGRFAC(P).
the flow dependent lHGR Muffip'fier.
LHGRFAC(F).
or the single loop operation (SLO) Multiplier if applicable.
The SLO muffipfier can befmmd in Table 5-3_ The LHGRFAC{P) is determined from Table 5-4_ The LHGRFAC(F) is detemunedfmm Tables 5-5 and 5-6, depending on plant condi!ions.
Tables 5-1 and 5-2 are the LHGR 6mit as a function of peak pellet exposure..
For Loss of 'FULL" Feedwater Heating (a change in temperature greater than 10 "'F, but less than or equal to 50 &deg;F FWTR). LHGRFAC(P) is determined from Table 5-7 and LHGRFAC(f) is detennined from Tables 5-8 and 5-9, depending on plant comfllions.
Concurrent operation with SLO and reduced feedwater heating has not been evaluated and thus is not a valid operating mode. (Reference
: 8) Page 17 of26 E&1DnNudear-NudearFue1s Cl.1ct9CmeOpe,atin!JUmilsRepmt Table5-1 UnearHeatGeneJa1ionRatel.imilsforU~Rods 1 (Refe,e~-4211129)
Fue1Type lHGRUmit See Table 8-1 ol *Refemnceg TabJe5-2 Linear Heat Generation Rat.e Umi1:s for Gad Rods 1 (Referern:es 4 and 9) Fu.eltype LHGRUmit GNF2 See Table B-2 of Reference9 TableS-3 UIGR Single Loop Operation (SLO) Multiplier (Reference
: 3) Fuel Type GNF2 1 Linear interpolation should be used for points not listed in the table. Page 18 of26 Ee1Dnfmdsar..:NmlearFne1s Q.1Cl9Com~linmsiRe;md DDC!1D:C0l.Rain1Dn 1 Re,_ 13 Core EGOS Row (%of .. Rated) IBaseCase
<50 DlOISLO 250 PROOSJPWOOS
<50 DlatSLO 250 TwoorMore
<50 TBVOOS. Dl.0/SLO .!!:50 Notes for TabJe 54: Talde54 PcmerDependentUIGRMdip'limsUIGRFAqpJ"' (iM:R:lme3)
Com DeJma1 Powar(%1 . . . 0..0 21..6 S33.3 >313 40..0 43.3 SD.O :,eu c . LHGRFAC !Pl ..* . 0.634 0.634 0~689 ' 0..651 -0.684 --D.572 0.572 0.600 0..560 0.560 0.560 0.500 0.550 -0.709 a749. 0.560 0.560 0..560 0.634 0.634 0.689 0.651 0.684. -.,. -0.572 0.572 0.600 1. Linear interpolation should be used for points not fisted in the table. Page19 of26 SSU* >85.G --0.868 o~soe --188..8 1.000 1.000 1.000 Eebmlmdear-iftm::learFels Cl.1C19ComOJ)&#xa3;!JillinD UmilsRepoJt TableH RowDapenden'tl.HGRIIIBJ1ip1imsLHGRFACfFjfm"BaseCaseorP.ROOSIPUIOOS 11 (Re1elem:e3)
ComRow LHGRFAC(FI
(%rcited) 0.0 0.442 . 25.0 0..612 30.0 0.646 822 1.000 109.0 1.000 Table~ Flow Dependent LHGR Multipliers LHGRFAC(F) for Two or More TBVOOS 1 (Reference
: 3) CoreAow LHGRFAC(F)
(% rated) .0.0 0.140 25.0 0.365 30.0 .* 0.410 40.0 0.500 50.0 0.630 80.0 0.860 98.3 1.000 109.0 1.000 1 Linear interpolation should be used for points not listed in the table. Page20 of26 Exe1an iNDdem-NudearFuels a.1ct9Cme0,perafins UmilsRepmt OOCRCOlRClintml1 Rev.13 Core !EOOS Flow Combination
(%of Rated) <50 Base Case DLO ~50 PROOSJPWOOS
<50 DLO ~50 TwoorMore
<50 TBVOOSDLO
~50 Notes for Table 5-7: TableS-7 Power Dependent LHGR!Nlultipliers LHGRFAC(P) (Loss of "FULL" Feedwater Heating)1 ,2 (Reference
: 3)
* Com Tbenmd Pawer(l'Ail 0..0 21..6 S33.3 >33.3 40.0 43.3 &sect;0.8 LHGRFAC[P) 0.628 0.628 0.682 0.644 -0.611 -0.566 0.566 0.594 0.554 0.554 0.554 0.554 0.554 -0.702 0.554 0.554 0.554 0.628 0.628 0.682 .0.644 -O.ol7 -0.556 .0.566 0.594 >60.8 gs_o >85.0 ---0.742 0.859 0.897 ---1. Values in Table 5-7 are determined by applying the required 1% adjustment from Appencfix E of Reference 3 to the values provided in Table 5-4. 2. Linear interpolation should be used for points not listed in the table. 100..0 0.990 0.990 0.990 3. Concurrent operation with SLO and reduced feedwater heating has not been evaluated and thus is not a valid operating mode (Reference 8). Page21 of 26 i 
!&e1ontmdear-NudsarFae1s Cl..1Cl90me0pera1ir-silim1JsRepo4 TableS-8 RowDapendentUIGRMD1tip1JeJs LffGRFAqFJfDrBaseCaseorPROOSfPWODS (lossoJ,=uJJ..*Feedwalm Heating)1 {Refelamie3)
CmeFlow UIGRFACfF) f'lf,mted) 0.0 0.438 25.0 . 0.60& 30.0 0..640 82.2 OJmD 109.0 0.990 Tab1e5-9 Flow Dependent UfGRMultiptiers LHGRFAC(F) for Two or Mom lBVOOS (Loss on=uu_* Feedwaler Heating)1 . (Refmem:e 3} CoreFJow LHGRFAC(F)
(% rated) 0.0 0.139 25.0 0.361 30.0 0.406 40.0 0.495 50.0 0.624 80.0 0.851 98.3 0.990 109.0 0.990 1 Linear interpolation should be used for points not listed in the table. Page22 of26 
&e1rm lludear-fmdearFm!ls CUCl9Com0,pmafinJ1 Um1ls RepDJt 6..0 Reactor Pmtedion System (RPS) llnslmmenlalion 6_ 1 Technical Specification Refaence:
SectioJI 3.3-1-1 6-2
 
== Description:==
 
The Average Pmver Range Monitor (APRM) flow biased simulated thenna1 power-high time constant, sha1J be be1ween 5.4 seconds and 6.6 seconds (References 6 and 11). 7.0 Turbine Bypass System ParameteJS 7.1 Technical Specification
 
==Reference:==
 
Section 3.7.6 7.2
 
== Description:==
 
The operability requirements for the Main Turbine Bypass System are governed by Technical Specification 3.7.6. If the requirements of LCO 3.7.6 cannot be met, the appropriate reactorthennal power, minimum critical power ratio (MCPR), and linear heat generation rate (LHGR) limits must be used to comply with the assumptions in the design basis transient analysis.
Table 7-1 provides the reador thennal power limitations for an inoperable Main Turbine Bypass System as specified in Technical Specification LCO 3.7.6. The MCPR and LHGR limits for one TBVOOS are included in the Base Case, as identified in Table 9-1. The MCPR and LHGR limits for two or more TBVOOS are provided in Sections 4 and 5. Table 7-1 Reactor Power Limitation
-Turbine Bypass Valves Out of Service (References 2, 3, and 10) .. Turbine Bvnass Svstem Status Maximum Reador Thermal Power(% Rated} One Turbine Bypass Valve 100.0 Out of Service Two or More Turbine Bypass Valves 100.0 Out of Service Page23 of 26 Eekm6udear-NudearlFDels CL1C19ComOJ)ma1m!l l.imilsRepo.rt 8.0 Stahiffl&#xa5; P.mtedion Se1pmnts DOC ID: COLR CfiD!Dn 1 Rev. 13 8.1 Technica1Spedfica1ilmReferem:e:
Sedion 3.3.1..3 82 Dasaipfitm:
The OPRM Period Based Detection At,gomhm (PBDA) Trip Selpomt fortbeOPRM System for use in Technical Specffiralion 3..3.1..3 is fmmd in Table 8-1. This va1ue is baseli oo lhe cycle spei:im:aim!Jsis documented in Refemnce 3-Slabffily-based 01.MCPR is non-fnniling for the PBDA setpoinl:
in Table 8-1. TabJe8-1 OPRM PBDA Trip Setpoint (Valid for AD Conditions) (Reference
: 3) PBDATripAmplitude Corresponding Maximum Confinnation Count Trip Setting . 16 Page 24of 26 Exelon /Nuclear-Nuclear Fuels CL1C19Core0perating Limits Report 9.0 Modes of Operation OOC ID: COlRCiinton 1 Rev. 13 The Allowed Modes of Operation with combinations of Equipment Out-of-Service (EOOS) are as described below in Table 9-1: EOOS Oplions 1 Base Case DLG3-4 Base Case SLOZ3 PROOSIPl.UOOS DLQ3.4.5 PROOSIPLUOOS SL~.5 Two or More lBVOOS DL0 4*6 TwoorMme1BV00SSla2-6 Notes: Tab1e9-1 Modes of Operation (Reference
: 3) Operatin,g Region Standard MEw.A ICF Yes Yes Yes Yes No No Yes Yes Yes Yes No No Yes Yes Yes Yes No No FFWTR2 Coastdown Yes Yes No Yes Yes Yes No Yes Yes Yes No Yes 1. A single Main Steam Isolation Valve {MSIV) out of service is supported at or below 75% power. {Reference
: 3) 2. Concurrent operation with SLO and Loss of 'FULL' Feedwater Heating {a change in temperature greater than 10 "F, but less than or equal to 50 "F FWTR), MELLLA, ICF, or FFWfR has not been evaluated and thus is not a valid operating mode. {Reference
: 8) 3. Includes 2 SRVOOS, 1 TCV stuck closed, 1 TSV stuck closed, 1 TBVOOS, and up to a 50"F feedwater temperature reduction
{FWTR includes feedwater heater OOS or final feedwater temperature reduction) at any point in cycle operation in Dual Loop mode. (Reference
: 12) 4. For operation with Loss of 'FULL' Feedwater Heating {a change in temperature greater than 10 "F, but less than or equal to 50 "F FWTR), the MAPLHGR is determined using the multiplier in Table 3-3 and the LHGR value is determined from Tables 5-7, 5-8, and 5-9. 5. Concurrent operation with either or both of PROOS + PLUOOS is allowed. 6. Includes 2 SRVOOS and up to a 50&deg;F feedwater temperature reduction
{FWTR includes feedwater heater OOS or final feedwater temperature reduction}
at any point in cycle operation in Dual Loop mode. {Reference 12} 7. End-of-cycle power coastdown operation down to 40% reactor power is supported by Methodology Reference
: 1. Coastdown operation beyond the EOR condition is conseivatively bounded by the reload licensing analyses at the EOR condition for a normal coastdown power profile. During coastdown, operation at a power level above that which can be achieved (at all-rods-out with all cycle extension features utilized, e.g., ICF, FFWTR) with steady-state equilibrium xenon concentrations is not supported. (Reference
: 3) Page25 of 26 l&.ekm lffndear-lNudearFllels Cl.1Cl9Cam0J)el21m.g Umils RepnJt DOCIID:COlRCfinhm 1 Rs.13 Theanaljlica"lme11mds userltodel.eimmellhemre~
timilsshallbafimse~mmewa'land apprmred byfhe NRC,, spacffica1JJtimsedescnlmd in the fo'lblrmlJJ documem: 1. GlliE1 ftJudaar Fuel 0m:umem. 'Genaia1 Bedric StmmRI Apprtralitm fm' ReactarFud (GESTAR Of,, NEDE-24011-P-Aa>, .lamsaty2018am:I US. Suppmenl NEDE-24011-P-A-26-US. .Jaiiuary2018.
11.0 Refemnces
: 1. NuctearRegu]almyCommission.
Tedmica1 Specifica1ions for Ctimon Pawar Slafioo Unit 1. Dm:ke1 No. 50-461. License No. NPF-62..
* 2. GE Hitami Nudear Eneigy RepoJt,, OOOD-ODBS-4634-R2-P Revision 1. Power Sta1ion One Bypass Out of SeMce or Turbine Bypass System Out of SennceAnalysis-Fma1." July2010.
: 3. GJobaJ Nuclear Fuel Document,.
004N2112 Revision D. -Supptemenlal Reload Ucensin9 Repmt for Cfinton Unit 1 Reload 18 Cycle 19; March 2018.
* 4, Global Nuclear Fue1 Document.
004N2113 Revision o. aFue1 Bundle Information RepOJt for Clinton Unit 1 Reload 18 Cycle 19; March 2018. 5. General Eleclric Document.
GE-NE-0000-0000-745S-01P, moption B Scram T1mes For Clinton Power Station,*
February 2002. 6. Exelon Transmittal of Design lnfonnation.
TODI ES1700024 Revision 1, "Fmal Resolved OPL-3 Parameters for Clinton Unit 1 Cycle 19,* January 16. 2018. 7. GE Hitachi Nuclear Energy Letter, CFL-EXN-LH1-12-059, *Affirmation of the crmton Power Station Unit 1 MAPLHGR Reduction for Feedwater Riser Flow Asymmetry; Apnl 25. 2012. 8. General Electric Document, GE-NE-0000-0026-1857-R1 Revision 1, *evaluation of Operation With Equipment Out Of Service for the Clinton Power Station,*
June 28, 2004. 9. Global Nuclear Fuel Document, NEDC-33270P, Rev. 9, aGNF2 Advantage Generic Compliance with NEDE-24011-P-A (GESTAR II),&deg; December 2017. 10. GE Hitachi Nuclear Energy Report, 003N4558-RO, aRemoval of TBSOOS Power Restriction for Clinton," March 10, 2016. 11. General Electric Document, 22A3167, Rev. 6, uNeutron Monitoring System-Solid State Safety Option,* December 22, 1988. 12. Exelon Transmittal of Design Information, TODI NF173316 Revision 0, aClinton Unit 1 Cycle 19 Customer Approved FRED Form," October 9, 2017. Page26 of26}}

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