ML12020A065

Submittal of the Core Operating Limits Report for Clinton Power Station, Unit 1, Cycle 14

ML12020A065
Person / Time
Site:	Clinton
Issue date:	01/04/2012
From:	Bradley Davis Exelon Nuclear, Exelon Generation Co
To:	Document Control Desk, Office of Nuclear Reactor Regulation
References
U-604047
Download: ML12020A065 (60)

Text

{{#Wiki_filter:Attachment 1 Contains Proprietary Information Withhold From Public Disclosure Under 10 CFR 2.390(a)(4). When Separated From Attachment 1, Cover Letter is Decontrolled. Exelon.Nuclear Clinton Power Station 8401 Power Road Clinton, IL 61727 U-604047 January 4, 2012 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 NRC Docket No. 50-461

Subject:

Submittal of the Core Operating Limits Report for Clinton Power Station, Unit 1, Cycle 14 In accordance with Technical Specification 5.6.5, "Core Operating Limits Report (COLR)," Item d., Exelon Generation Company (EGC), LLC is submitting the COLR for Clinton Power Station, Unit 1, Cycle 14. Attachment 1 contains a proprietary version of the COLR that is requested to be withheld from public disclosure in accordance with 1 OCFR2.390(a)(4). This submittal is subdivided as follows: 1. Attachment 1 provides a proprietary version of the COLR. Appendix A of this attachment contains an affidavit that attests to the proprietary nature of the information contained in the document.2. Attachment 2 contains a non-proprietary version of the COLR documented in Attachment 1.Should you have any questions concerning this report, please contact me at (217) 937-2800.Attachment 1 Contains Proprietary Information Withhold From Public Disclosure Under 10 CFR 2.390(a)(4). When Separated From Attachment 1, Cover Letter is Decontrolled. / PC Attachment 1 Contains Proprietary Information Withhold From Public Disclosure Under 10 CFR 2.390(a)(4). When Separated From Attachment 1, Cover Letter is Decontrolled. U.S. Nuclear Regulatory Commission U-604047 Page 2 of 2 Respectfully, Brian W. Davis Regulatory Assurance Manager Clinton Power Station JLP/blf Attachments:

1. Core Operating Limits Report for Clinton Power Station Unit 1, Cycle 13 (Proprietary Version)2. Core Operating Limits Report for Clinton Power Station Unit 1, Cycle 13 (Non- Proprietary Version)cc: NRC Regional Administrator, Region III NRC Senior Resident Inspector

-Clinton Power Station Attachment 1 Contains Proprietary Information Withhold From Public Disclosure Under 10 CFR 2.390(a)(4). When Separated From Attachment 1, Cover Letter is Decontrolled. Attachment 1 Contains Proprietary Information Withhold From Public Disclosure Under 10 CFR 2.390(a)(4). When Separated From Attachment 1, Cover Letter.ý is Decontrolled., ATTACHMENT 2 Core Operating Limits Report for Clinton Powe. Station Unit,1,.Cycle 14 (Non-Proprietary Versiopn)Attachment 1 Contains Proprietary Information Withhold From Public Disclosure Under 10 CFR 2.390(a)(4). When Separated From Attachment 1, Cover Letter is Decontrolled. Exelon Nuclear- Nuclear Fuels CLI C14 Core Operating LjmitS Report Non-Pro4 ay hIfonma submitted In Aceordance witil 10 CFR 2.3-0 DOC ID: COLR Clinton I Rev. 6 CORE OPERATINGL UMITS REPORT FOR CLINTON POWER STATION UNOT "i CYCLE 14 Prepared By: :31~-~tZ, lt Oaler'I&ad(-sMLai R. Holmes Reviewed By: ----_-RF Riulu~w~r Reviewed By: Reviewed By:.AiIU~ EiC 1 W ESA Rfevie~er Independ~weieir Date: 1 -Date: Date: 1 7 /11 Date: I;L.//f Approved By:. C I fJamesJ.Station QuaBif1i ")<'4!Reviewer By: " a4Z2..Date: hL?7!L/Date: / ic; /-- .!Page 1 of 57 Exelon Nuclear -Nuclear Fuels DOC ID: COLR Clinton 1 Rev. 6 CLIC14 Core Operating Limits Report Non-Proprietary Information Submitted in Accordance with 10 CFR 2.390 Table of Contents 1.0 Terms and Definitions 5 2.0 General Information 7 3.0 MAPLHGR Limits 8 4.0 MCPR Limits 10 5.0 Linear Heat Generation Rate Limits 17 6.0 Reactor Protection System (RPS) Instrumentation 23 7.0 Turbine Bypass System Reactor Power Limitation 23 8.0 Stability Protection Setpoints 23 9.0 Modes of Operation 24 10.0 Methodology 25 11.0 References 25 Appendix A 26 Page 2 of 57 Exelon-Nuclear -Nuclear Fuels .,., DOC ID:.COLR Clinton 1 Rev. 6 CLLC14 Core Operating Limits Report Non-Proprietary Information Submitted in Accordance with 10 CFR 2.390 List of Tables Page Table 3-1 MAPLHGR Versus Average: Planar Exposure,:.-GE14C/GE141: 8&Table 3-2 MAPLHGR Versus Average Planar Exposure -GNF2 8 Table 3-3 MAPLHGR Single Loop Operation (SLO) Multiplier' 9 Table 4-1. Operating Limit Minimum Critical Power Ratio-., -12 Table 4-2 Power Dependent MCPR Limits MCPR(P) and MultipliersJK(P) 13 Table 4-3. PROOS Power Dependent MCPR Limits MCPR(P) and Multipliers K(P). 14 Table 4-4 Dual Loop Operation (DLO) Flow Dependent MCPR Limits MCPR(F) 15 for Base Case/PROOS Table 4-5 Single Loop Operation (SLO) Flow Dependent MCPR Limits MCPR(F) 15 for Base Case/PROOS Table 4-6 Dual Loop Operation (DLO) Flow Dependent MCPR Limits MCPR(F) 16 for TBSOOS Table 4-7 Single Loop Operation (SLO) Flow Dependent MCPR Limits MCPR(F) 16 for TBSOOS Table 5-1 Linear Heat Generation Rate Limits for U0 2 Rods 18 Table 5-2 Linear Heat Generation Rate Limits for Gad Rods 18 Table 5-3 Power Dependent LHGR Multiplier LHGRFAC(P) 19 Table 5-4 Flow Dependent LHGR Multiplier LHGRFAC(F) for Base Case/PROOS 20 Table 5-5 Flow Dependent LHGR Multiplier LHGRFAC(F) for TBSOOS 20 Table 5-6 LHGR Single Loop Operation (SLO) Reduction Factor 20 PFage 3 of 57 Exelon Nuclear -Nuclear Fuels DOC ID: COLR Clinton I Rev. 6, CLIC14 Core Operating Limits Report Non-Proprietary Information Submitted in Accordance with 10 CFR 2.390 Table 5-7 Power Dependent LHGR Multiplier LHGRFAC(P) (Loss of'FULL' 21 Feedwater Heating)Table 5-8 Flow Dependent LHGR Multiplier LHGRFAC(F) for Base Case/PROOS 22 (Loss of 'FULL' Feedwater Heating)Table 5-9 Flow Dependent LHGR Multiplier LHGRFAC(F) for TBSOOS (Loss of 22'FULL' Feedwater Heating) ..Table 7-1 Reactor Power Limitation -TBSOOS-s':.' 23 Table 8-1 OPRM PBDA Trip Setpoints

23'Table 9-1 Modes of Operation

.24.Page 4 of 57 Exelon Nuclear -. Nuclear Fuels DOC ID: COLR Clinton I Rev. 6 CLIC14 Core Operating Limits Report Non-Proprietary Information Submitted in Accordance with 10 CFR 2.390 1.0 Terms and Definitions ADSOOS Automatic Depressurization System Valve Out of Service Base Case A case analyzed with two (2) Safety-Relief Valves Out-of-Service (OOS), one (1)Automatic Depressurization System valve OQS, one (1) Turbine Control Valve stuck closed, one (1) Turbine Stop Valve stuck closed, one (1) Turbine Bypass Valve OOS, and up to a 50°F feedwater temperature reduction, (FWVýT-R includes feedwater heater OOS or final feedwater temperature reduction) at any point in the cycle operation in Dual Loop mode (Reference 3)._Coastdown The reactor condition where thermali power gradually decreases due to fuel depletion while the following conditions are met: 1) all operable control rods are fully withdrawn and 2) all cycle extension techniques have been exhausted including FFWTR and ICF.DLO Dual Reactor Recirculation Loop Operation FFWTR Final Feedwater Temperature Reduction FWHOOS Feedwater Heaters Out of Service ICF Increased Core Flow LHGR Linear Heat Generation Rate LHGRFAC(F) LHGR thermal limit flow dependent multipliers LHGRFAC(P) LHGR thermal limit power dependent multipliers MAPLHGR Maximum Average Planar Linear Heat Generation Rate MCPR Minimum Critical Power Ratio MCPR(F) MCPR thermal limit flow dependent adjustments and multipliers MCPR(P) MCPR thermal limit power dependent adjustments and multipliers MELLLA Maximum Extended Load Line Limit Analysis MSIV Main Steam Isolation Valve OLMCPR Operating Limit Minimum Critical Power Ratio OPRM Oscillation Power Range Monitor PROOS Pressure Regulator Out of Service Page 5 of 57 Exelon Nuclear -Nuclear Fuels DOC iDb COLRClinton I Rev. 6 CLIC14 Core Operating Limits Report Non-Proprietary Information Submitted in Accordance with 10 CFR 2.390 SLO Single Reactor Recirculation Loop Operation SRVOOS Safety Relief Valve Out of Service TBVOOS Turbine Bypass Valve Out of Service -'one valve TBSOOS ' Turbine-Bypass System Out of Service, TCVOOS Turbine Control Valve Out ofUService -one Valve TSVOOS Turbirne stop Valve Out'bf service --one valve-Page 6 of 57 Exelon Nuclear- Nuclear Fuels DOC ID: COLR Clinton 1 Rev. 6 CLIC14 Core Operating Limits Report Non-Proprietary Information Submitted in Accordance with 10 CFR 2.390 2.0 General Information This report is prepared in accordance with Technical Specification 5.6.5 of Reference

1. Power and flow dependent limits and multipliers are listed for various power and flow levels. Linear interpolation is to be used to find intermediate values.These values have been determined using NRC-approved methodologies presented, in Section ,10 and are established such that all applicable limits of the plant safety analysis are met.* .The data presented in this report is valid for all .licensed operating

'domains on the operating map, including:

• Maximum Extended Load Line Limit down, to99%'df rated core flbw 'during full power operation* Increased Core Flow (ICE) up to 107% of rated core flow ," Final Feedwater Tmperature Reduýcti6n'IFVVTR) upto 50 0 Fdurng cycle extension operation* Feedwater Heater Out of s6r~ice(FWHObOS) upto 50 0 F' feedwater temperature reduction at any time during the cycle prior to cycle extension.

Page 7 of 57 Exelon Nuclear -Nuclear Fuels CLIC14 Core Operating Limits Report Non-Proprietary Information Submitted in Accordance with 10 CFR 2.390 DOC ID: CQLR Clinton I Rev. 6 3.0 MAPLHGR Limits 3.0 Technical Specification

Reference:

Sections 3.2.1 and 3.4.1.3.1 Descriptio ,.: ,. :: .".... Table 3-1 is used to determine the maximum average planar linear heat generation rate (MAPLHGR)..limit for GE1 4C and GE14 fuel. Table 3-2:. s used to determine the maximum average planar linear heat generation rate (MAPLHGR) limit for GNF2 fuel. Limits listed in Table 3-1 and Table 3-2 are for dual reactor recirculationloop operation (DLO)........, , For single reactor recirculation loop operation. (SLO), the,;MAPLH,ýGR limits given in Table 3-1 and Table 3-2 must be'multiplied b.ya SLb iAPIL'HGRmultiplierprovided'in Table 3-3. The SLO MAPLHGR multiplier for 6ll fuel types is 0.76 (Reference 3).Table 3-1 MAPLHGR Versus Average Planar Exposure -GE14C/GE1411 (Reference 3)Avg. Planar Exposure MAPLHGR Limit (GWd/ST) (kW/ft)0.00 12.82 19.13 12.82 57.61 8.00 63.50 5.00 Table 3-2 MAPLHGR Versus Average Planar Exposure -GNF2'(Reference 3)Avg. Planar Exposure MAPLHGR Limit (GWd/ST) (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 8 of 57 Exelon Nuclear.- Nuclear Fuels CLIC14 Core Operating Limits Report Non-Proprietary Information Submitted in Accordance with 10 CFR 2.390 DOC ID: COLR Clinton I Rev. 6 Table 3-3 MAPLHGR Single Loop Operation (SLO) Multiplier (Reference 3)Fuel MAPLHGR Type SLO Multiplier All Fuel Types 0.76 Page 9 of 57 Exelon Nuclear -Nuclear Fuels. DOC ID: COLR Clinton ! Rev. 6 CLIC14 Core Operating Limits Report Non-Proprietary Information Submitted in Accordance with 10 CFR 2.390 4.0 MCPR Limits 4.0 Technical Specification

Reference:

- Sections 3.2.2, 3.4.1, "and 3.7.6'4.1

Description:

.-.The various MCPR limits are described below.4.1.1 Manual Flow Control MCPR Limits The Operating Limit MCPR (OLMCPR) is determined from either section 4.1.1.1 or 4.1.1.2, whichever is greater at any given power and flow condition. 4.1.1.1 Power-Dependent MCPR For operation less than 33.3% core thermal power and with the pressure regulator in service, the MCPR(P) as a function of core thermal power is shown in Table 4-2. For operation less than 33.3% core thermal power and with the pressure regulator out of service, the MCPR(P)as a function of core thermal power is shown in Table 4-3.For operation at greater than or equal to 33.3% core thermal power, the OLMCPR as a function of core thermal power is determined by multiplying the applicable rated condition OLMCPR limit shown in Table 4-1 by the applicable MCPR multiplier K(P) given in Table 4-2 or Table 4-3. The Base Case (DLO and SLO) MCPR(P) and K(P) given in Table 4-2 are also applicable to the corresponding condition with TBSOOS (Reference 3).4.1.1.2 Flow-Dependent MCPR Tables 4-4 through 4-7 give the MCPR(F) as a function of flow based on the applicable plant condition. The limits for dual loop operation are listed in Tables 4-4 and 4-6. The limits for single loop operation are listed in Tables 4-5 and 4-7. The MCPR(F) determined from these tables is the flow dependent OLMCPR.4.1.2 Automatic Flow Control MCPR Limits Automatic Flow Control MCPR Limits are not provided.Page 10 of 57 Exelon Nuclear -NuqlearFuels, DOC ID: COLR Clinton I Rev. 6 CL1C14 Core Operating Limits Report Non-Proprietary Information Submitted in Accordance with 10 CFR 2.390 4.1.3 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 The Technical Specification scram speeds'must~be met to utilizpthe Option A M CFPR.limits. Reload analyses performed by GNF for CycJe 14 Option 4,jMCPR limits utilized a ;20% core average insertion time of.0. 516 seco~nds(.Reference' 6).To utilize the MCPR limits for the Option B scram;speed, the cycle average scram insertion time for 20% insertionmust satisfyequation 2 in Reference 5 Section 4: If thecycle'average scram insertion timedoes not meet.the Option B criteria, the appropriate MCPR value may be determined from a linearinterpolation between the Option A and B limits as specified by equation 4 in Reference 5 Section.4." S4.1.4 Recirculation Flow Control Valve Settings Cycle 14 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 (Reference 3).Page.11 of 57 Exelon Nuclear- Nuclear Fuels CL1014 Core Operating Limits Report Non-Proprietary Information Submitted in Accordance with 10 CFR 2.390 DOC ID: COLR Clinton 1 Rev. 6 Table 4-1 Operating Limit Minimum Critical Power Ratio (Reference 3)GE14Ct Fu-e' IEi4C Fuel GE141 ýFuel GEl41 7 Fuel GNF2 Fuel GNF2 Fuel EOos Option B.on iptionA Option B Option A Combination' ,AlIi -All " All All All Exposures Exposures', 'Exposures Exposures Exposures Base Case i. j4 -1 136 1.39 DL 6 1 11,43 1.43 .-1.36 1.36 Base Case. ....... ...." " " SLO 5 6 .-36 -1:38 :-, :143 ..1.45,. 1.36 .1.42 PROOS 1 ..DLO 6 1.36 1.36 1.43! 1.43 11.362 1.39 PROOS SLO 5.6 1.36 1.38 1.43 ..45 1.36 1.42-TBSOOS 3 ...136z.. .DLO 1:36 1.39 T 1.43 1.46- ' 1.36 1.42 TBSOOS 2 SLO 5 1.36 1.42 1.43 " 1.49 1.36

• 1.45 Notes for Table 4-1: 1. Analyzed DLO Option B OLMCPR is 1.25 per Reference 3, value is adjusted to obtain an OPRM amplitude setpoint of 1.10.2. Analyzed DLO Option B OLMCPR is 1.29 per Reference 3, value is adjusted to obtain an OPRM amplitude setpoint of 1.10.3. Analyzed DLO Option B OLMCPR is 1.32 per Reference 3, value is adjusted to obtain an OPRM amplitude setpoint of 1.10.4. Analyzed DLO Option A OLMCPR is 1.35 per Reference 3, value is adjusted to obtain an OPRM amplitude setpoint of 1.10.5. SLO Option A(B) OLMCPR is the transient DLO Option A(B) OLMCPR plus 0.03 or the OPRM OLMCPR value, whichever is highest.6. Includes TCV and/or TSV stuck closed, 1 TBVOOS.7. GE141 OLMCPR is the GE14C OLMCPR plus 0.07.' Page 1-2 of 57 Exelon Nuclear -Nuclear Fuels CLIC14 Core Operating Limits Report Non-Proprietary Information Submitted in Accordance with 10 CFR 2.390 DOC ID: COLR Clinton 1 Rev. 6 Table 4-2 Power Dependent MCPR Limnits MCPR(P) and Multipliers K(.)1'2 (Reference 3)EO Co" re Flow{ " ...Core ThermaliPoweir(%)

-,-EOOS (%of 0 ' .<70 >70 100*Combination. ..* -: Rated) 3M C p. __.... ) .......Base Case DLO < 50' 2:31'. 2.31 -.2-10 .- 121-. i1.. 1000 1:351 -1:163 1.000'GNF2/GE14C'ý > 50 24'Base Cas6-SLO 5 50 2.34 2.'34'4 -2..1"3 1.f... .ý'2:46. 1.16 .17"00 GNF2/GE14C 5 > 50' 24 .9:2 TBSOOS DLO < 50 2.:31 2.3'1 2.10'"J:351 -.1.212. .163 1.000 GNF2/GE14C, > 50 2.469 ;2.46J1.2.17 , i ...... _..TBSOOS SLO < 50 2.34. 2.34 : 2.113 1.351 1.212 1.163 1.000 GNF2/GE14C > 50 2.49 2.49 2.20 1 GE141 4.5 > 50 2.53 2.53 2.24 Base Case SLO < 50 2.41 2.41' 220 GE141 4'5 >50 256 2.56'.2.27 1.351 1.212 .1.163 -1.000 TBSOOS SLO .< 50 2.38, 2.38. 2.17 1.351 ' 1.163 1.000 GE14 > 50 2.53 2.536 2.24 TBSOOS SLO < 50 2.38, 2.38. 2:17-14351 1.212, 1,163 1.000 TBSOOS SLO < 50 2.41 2.41 2.20 1.351 14212 1.163 1.000 GE141 4 > 50 2.56 2.56 2.27 Notes for Table 4-2: 1. Values are interpolated between relevant power levels.2. Allowable EOOS conditions are listed in Section 9.0.3. Based on 0.500 second turbine trip time delay with OLMCPR > 1.27 (Reference 3).4. An adder of 0.07 is applied to the GE14/GNF2 MCPR(P) values for GEl41.5. Includes TCV and/or TSV stuck closed, 1 TBVOOS.Page 13 of 57 Exelon Nuclear -Nuclear Fuels" CLIC14 Core Operating Limits Report Non-Proprietary Information Submitted in Accordance with 10 CFR 2.390 DOC ID: COLR Clinton I Rev. 6 T a;ble 4-3 PRO0S PoWer Dependent MCPR Limits MCPR(P) and Multipliers K(P)1'2 (Reference 3)Core ..-Core Thermal Power (%)-Combination Flow (% .0 : 1.6,1 <33.3,, >33.3,1:, 60 1 <85 1 >185 100 ,f Rated)- MCPR(P [rn K(P)3 _-__PROOS DLO <-50 2'.31' 12l-:'2 10..558 1.436 1,.309 1.0841 1.000 GNF2/GE14C 5 >50 c-2.46 2.46 2.17 .. ....... ......PROOS SLO < 50 2;34. 2.34 2.13 1 16 0 8 0 GNF2/GE14C 5 > 50! 2.49 2.49, 220 PROOS DLO <50 ... 38' _2.3,_ ,2.217.... ......... .... ..:, .... :........... i 558' -1.436 *i1 .09 1.1084 .1.000 GE141 4 ,5 > 50 .2.53j 2.53 '2.24 1 1 1 100 PROOS SLO .< 50 2.41 2.41 '2.20 1558-----1.5 1.436 1.309 '1.084 1.000 GE141 4 ,5 .j>,50 2.56 2.56' 2.27 Notes for Table 4-3:-1. Values are interpolated between relevant power levels.: 2. Allowable EOOS conditions are listed in Section..9.0.* .3. Based on 0.500 second turbine trip time delay with O'LMCPR > 1.27.(Reference 3).4. An adder of 0.07 is applied to the GE14/GNF2MCPR(P) values for GEl41.5. Includes TCV and/or TSV'stuck closed, 1 TBVOOS..Page 14 of 57 Exelon Nuclear -Nuclear Fuels CLIC14 Core Operating Limits Report Non-Proprietary Information Submitted in Accordance with 10 CFR 2.390 DOC ID:,COLR Clinton 1 Rev. 6 Tablei4-4m Dual Loop Operation (DLO) Flow Dependent MCPR Limits MCPR(F) for Base Case/PROOS'(Reference 3)Core Flow .'MCRPI(F) [-.;MCPR(F) (% rated).. GNF2/GE14C 1_ .GEl41 r 0.0, 1.8819 .1.9519'25.0 1.i.70 1.77.84A1 .1.27 .93.721I '. ..... .1.27 109.0 1.27 1.27 Table 4-5 Single Loop Operation (SLO) Flow Dependent MCPR Limits MCPR(F) for Base Case/PROOS 1 (Reference 3)Core Flow MCPR(F) -MCPR(F)(% rated) .GNF2/GE14C GE141 0.0 .1.9119 1.9819 25.0 1.73 1.80 t 84.1 2. 1:30 "_ '- _93.721 -1.30 109.0 1.30 1.30 Linear interpolation should be used for points not listed in the table.,-Page 15 of 57 Exelon Nuclear'- Nuclear Fueis ..CLIC14 Core Operating Limits Report Non-Proprietary Information Submitted in Accordance with 10 CFR 2.390 DOC ID: COLR Clinton I Rev. 6 Table 4-6 Dual Loop Operation (DLO) Flow Dependent MCPR Limits MCPR(F) for TBSOOS 1 (Reference 3):.Core Flow MCPR(F) MCPR(F) j GNF2/GEI4C 7 GE141 0 .20433. .. -.21.133.25 -1.85 1.92..100 -. .. ." 1_27 ..: -. .109 1.27..100 .'" 1.27 .. 1.27.Table 4-7 Single Loop Operation (SLO) Flow Dependent MCPR Limits MCPR(F) for TBSOOS 1.(Refe'rence 3)Core Flow MCPR(F) MCPR(F)(% rated)' GNF21GEI:4C.. GEI410 2.0733 .2.1433 25 .1.88 .1.95-100 .1.30 j* 109

• 1.30 j 1:30 Linear interpolation should be used for points not listed in the table.Page 16 of 57 Exelon.Nuclear Nuclear Fuels DOC ID: COLR Clinton 1 Rev. 6 CLLC14 Core Operating Limits Report Non-Proprietary Information Submitted in Accordance with 10 CFR 2.390 5.0 Linear Heat Generation Rate Limits 5.1 Technical Specification

Reference:

-Section 3.2.3, 3.4.1, and 3.7.6.5.2

Description:

The linear heat generation rate (LHGR) limit is the product, of the exposure dependent LHGR limit (from Table 5-1 for U02 fuel rods and Table 5-2'for Gadolinia fuel rods) and the minimum of: the power dependent LHGR Factor, LHGRFAC(P), the flow dependent LHGR Factor, LHGRFAC(F), or the single loop operation (SLO) multiplication factor if applicable. The LHGRFAC(P) is determined from Table 5-3. The LHGRFAC(F) is determined from Tables 5-4 and 5-5, depending on plant conditions. The SLO multiplication factor can be found in Table 5-6. Tables 5-1 and 5-2 are the LHGR limit as a function of peak pellet exposure.The Gadolinia fuel rod limits referenced in Table 5-2 are the most limiting Gadolinia fuel rods. The most limiting values are provided here as a convenience and do not imply that all the Gadolinia fuel rods must satisfy the listed values.For Loss of 'FULL' Feedwater Heating (+/-10 'F outside design NORMAL temperature), LHGRFAC(P) is determined from Table 5-7 and LHGRFAC(F) is determined from Tables 5-8 and 5-9, depending on plant conditions. Concurrent operation with SLO and reduced feedwater heating has not been evaluated and thus is not a valid operating mode. (Reference 3)Page 17 of 57 Exelon Nuclear -Nuclear Fuels"'CL1C14 Core Operating Limits Report Non-Proprietary Information Submitted in Accordance with 10 CFR 2.390 DOC ID: -COLR Clinton' Rev. 6 Table 5-1 Linear Heat Generation Rate Limits for U0 2 Rods!(Reference 4)Fuel Type LHGR Limit.GNF2 See Appendix.A GE!4c, See ,Appendix A GE14I See Appendix A.'. .','". " .' "'i Table 5-2 Linear Heat Generation Rate Limits for Gad Rods 1 (Reference.4) Fuel Type] LHGR Limit GNF2 See Appendix A GE14C See Appendix A GE141 See Appendix A 1 Linear interpolation should be used for points not listed in the table.Page 18 of 57 Exelon Nuclear- Nuclear Fuels. : CLIC14 Core Operating Limits Report Non-Proprietary Information Submitted in Accordance with 10 CFR 2.390 DOC ID: COLR Clinton I Rev. 6 Table 5-3 PowerDependent LHGR Multiplier LHGRFAC(P) 2 I (Reference 3)_ _Core Thermal Power (%)Core .EOOS Flow Combination (% of 0.00"- <33.3;: >33.3 40.0 <60.0 >60.0 100.0 Rated) _ _ _. ... _ _, __" ..... ._ _ _i_____ _____-____ .. LHGRFAC(P) Base Case < 50 ý0.634-ý' 0.634. 0.68'9 O 50M651 --1.000 DLO _ > 50 0.600. ........__Base Case < 50 0.634 0.634 0.689 SLO 1 > 50 0.572 0.572 0.600 0.651 1.0 TBSOOS < 50 0.634 0.634, -.0.689 0.651 -1 DLO "j >50 0.572 0572:- 0'600 " _-" ___' I TBSOOS < 50 0.634 0.634 0.689 0.651 1.000 SLO > 50 0.572 0:572 '0.600 _ _PROOS <50 0560 0560' 0560 0560 0.560 0.709 0.749 1.000 DLO > 50 0:560 0.560, 0.560 -PROOS < 50 0.560- 0.560 0.560 0 SLO 1> 50 0.560 0560 0.560 0.560 0.709 0.749 1.000 Notes for Table 5-3: 1. Includes TCV and/or TSV stuck closed, 1 TBVOOS.2. Linear interpolation should be used for points not listed in the table.Page 19'of 57 Exelon Nuclear -Nuclear Fuels CLIC14 Core Operating Limits Report Non-Proprietary Information Submitted in Accordance with 10 CFR 2.390 DOC ID:-COLR ClintOn 1 Rev..6ý- -Tabie 5-4 Flow Dependent LHGR Multiplier, LHGRFAC(F) for Base Case/PROOS'(Reference 3)Core Flow1 (% rated) j LHGRFAC(F) 001 0.442'25.0 0.612 30.0 0.646'82., 1.000" Table 5-5 .Flow Dependent LHGR Multiplier LHGRFAC(F) for (Reference-3) TBSOOS'Core Flow J L'"GR FIC'FA 1 (% rated) ..:0.0 0:140, 25.0 0.365 30.01 0.410 40.0 0.500 50.0 0.630 80.0 0.860 98.3 1.000 109.0 1.000 Table 5-6 LHGR Single Loop Operation (SLO) Reduction Factor (Reference 3)Fuel LHGR Type SLO Multiplier All Fuel Types 0.76 Linear interpolation should be used for points not listed in the table.Page 20 of 57 Exelon Nuclear -Nuclear Fuels. DOC, ID: COLR Clinton I Rev. 6 CL1C14 Core Operating Limits Report Non-Proprietary Information Submitted in Accordance with 10 CFR 2.390 Table 5-7 Power. Dependent LHGR Multiplier LHGRFAC(P)(Loss of 'FUL L'Feedwater H1ea-ting) 2 (Reference 3)Core Thermal Power (%)Core Co on Flow (% 0... 21.6, -,<33.-3:

,->33 40 <60 >60 100 Combination ofRtd ____I___{33

_______________ of Rated) ,__- -----. -- LHGRFAC(P) Base Case <50 0.62766 0.62766 0.682110.644 0.0.64449 -0.99000 DLO 1 > 50 0.56628 0.56628 0'59400 .... __Base C~ase< ____ ___ ___ ___SLO TBSOOS DLO< 50 0.62766 0.62766 0.68211 0.64449 0.99000 SU.=44U 1U.0441 U.44U 0.55440 0.55440 0.70191 0.74151 0.55440. 0.55440 0.55440 1 1 1 Notes for Table 5-7: 1. Includes TCV and/or TSV stuck closed, 1 TBVOOS. " 2. Linear interpolation should be used for points not listed in the table.page 21 of 57 Exelon Nuclear -Nuclear Fuels ..CLIC14 Core Operating Limits Report Non-Proprietary Information Submitted in Accordance with 10 CFR 2.390 DOC iD:! COLR Clinton' I Rev. 6 Table 5-8 Flow Dependent LHGR Multiplrier'LHGRFAC(F) for Base Case/PROOS (Lorssbf 'FULL' Feedwater Heating)1 (Reference 3)Core Flow L -.HG-.RFACF..(% rated),. LGF 0.,0 0.43758 25.0 0.60588.30.0ý:" I 0.63954 82.2' 0.990 109.0(:1. "0990-, , Table 5-9 Flow Dependent LHGR Multiplier LHGRFAC(F) for TBSOOS (Loss of 'FULL' Feedwater Heating)1 (Reference 3)Core Flow- 1 ( Flo LHGRFAC(F) (% rated)0.0 0.1386 25.0 0.36135 30.0 0.4059 40.0 0.495 50.0 0.6237*80.0 ' 0.8514'98.3 0.990 109.0 0.990 1 Linear interpolation should be used for points not listed in the table.Page 22 of 57 Exelon Nuclear -, Nuclear Fuels DOC ID: COLR Clinton 1. Rev. 6 CL1014 Core Operating Limits Report Non-Proprietary Information Submitted in Accordance with 10 CFR 2.390 6.0 Reactor Protection System (RPS) Instrumentation 6.1 Technical Specification

Reference:

Section 3.3.1.1 6.2

Description:

The Average Power Range Monitor (APRM) simulated thermal power time constant, shall be between 5.4 seconds a4nd6.6 seconds (Reference 6).7.0 Turbine Byp'ass System Reactor Power Limitation " 7.1 Technical Specification

Reference:

Section 3.7.6 7.2-

Description:

Table 7-1 provides the maximum allowable reactor power with TBSOOS as specified in Technical Specification 3.7.6 action statementA.l.. Table 7-1 Reactor Power Limitation --TBSOOS (Reference 3)II Turbine Bypass System Status I Maximum Reactor Power (% Rated)TBSOOS 97.0 8.0 Stability Protection Setpoints k The Clinton 1 Cycle 14 OPRM Period Based Detection Algorithm (PBDA) Trip Setpoints for the OPRM System for use in Technical Specification 3.3.1.3 are found in Table 8-1. These values are based on the cycle specific analysis documented in Reference 3.Any change to the OLMCPR value and/or ARTS-based power dependent MCPR limits should be evaluated for potential impact on the OPRM PBDA Trip Setpoints. Table 8-1 OPRM PBDA Trip Setpoints (Reference 3)PBDA Trip Amplitude Corresponding Maximum Confirmation I Tp Count Trip Setting 1.10 1 13 Page23 of 57 Exelon Nuclear -Nuclear Fuels CLI C14 Core Operating Limits Report Non-Proprietary Information Submitted in Accordance with 10 CFR 2.390 DOC ID:COLR Clinton 1 Rev. 6 9.0 Modes of Operation The Allowed Modes of Operation with combinations of Equipment Out-of-Service (EOOS) are as described below in Table 9-1: Table 9-1 Modes of Operation (Reference 3)Operatiing Region EOOS Options 2 Standard MELLLA,. ICF FFWTR' Coastdown Base Case DLO 3 Yes 'Y' es Yes Yes Base Case SLO 1'3 Yes No ... .. , No *No. Yes PROOS DLO 3 Yes Yes Yes Yes Yes PROOS SLO 1'3 Yes No No No Yes TBSOOS DLO 4 Yes Yes Yes Yes Yes TBSOOS SLO 1'4 Yes No No 'No *Yes Notes: 1. Concurrent operation with SLO and Loss of'FULL' Feedwater'Heating (+/-10°F outside design NORMAL temperature) or FFWTR has not been evaluated and thus is not a valid operating mode. (Reference 3)2. A single Main Steam Isolation Valve (MSIV) out of service is supported at or below 75% power. (Reference 3)3. Includes 2 SRVOOS, 1 ADSOOS, 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 Lo0p mode.4. Includes 2 SRVOOS, 1 ADSOOS, 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 inDUal Loop mode. ': :.Page 24 of 57 Exelon Nuclear- Nuclear Fuels DOC ID: COLR Clinton 1 Rev. 6 CLIC14 Core Operating Limits Report Non-Proprietary Information Submitted in Accordance with 10 CFR 2.390 10.0 Methodology The analytical methods used to determine the core operating limits shall be those previously reviewed and approved by the NRC, specifically those described in the following documents:

1. Global Nuclear Fuel Document, "General Electric Standard Application for Reactor Fuel", NEDE-24011-P-A-18-US, April 2011 and U.S. Supplement NEDE-24011-P-A-18-US, April 2011.2. "BWR Owners' Group Reactor Stability Detect and Suppress Solutions Licensing Basis Methodology and Reload Applications", NEDO-32465, August 1996 11.0 References

1. Nuclear Regulatory Commission, Technical Specifications for Clinton Power Station Unit 1, Docket No. 50-461, License No. NPF-62.2. Unused.3. Global Nuclear Fuel Document, 0000-0127-2441-SRLR Revision 1, "Supplemental Reload Licensing Report for Clinton Power Station Unit 1 Reload 13 Cycle 14", November 2011.4. Global Nuclear Fuel Document, 0000-0127-2434-FBIR-NP Revision 0, "Fuel Bundle Information Report for Clinton Power Station Unit 1 Reload 13 Cycle 14", October 2011.5. General Electric Document, GE-NE-0000-0000-7456-01P, "Option B Scram Times For Clinton Power Station", February 2002.6. Exelon Transmittal of Design Information, TODI ES1 100019 Revision 1, "Resolved OPL-3 Parameters for Clinton Cycle 14 ", August 22, 2011.Page 25 of 57 Exelon Nuclear -Nuclear Fuels CLIC14 Core Operating Limits Report Non-Proprietary Information Submitted in Accordance with 10 CFR 2.390 DOC ID: COLR Clinton fik Rev. 6 Appendix A Page- 26 of 57 Exelon Nuclear -Nuclear Fuels.-CLIC14 Core Operating Limits Report Non-Proprietary Information Submitted in Accordance with 10 CFR 2.390 DOC ID: COLR Clinton I Rev. 6 GNF Global Nuclear Fuel Global Nuclear Fuel A Joint Venture of GEToshiba, & Hitachi 0000-0127-2434-FBIR-NP Revision 0 Class I October 2011.1..,*Non-Proprietary Information

-Class I (Public)Fuel Bundle Information Report for Clinton Power Station Unit 1 Reload 13 Cycle 14 Copyright 2011 Global Nuclear Fuel -Americas, LLC All Rights Reserved Page 27 of 57 Exelon Nuclear -Nuclear Fuels CLIC14 Core Operating Limits Report Non-Proprietary Information Submitted in Accordance with 10 CFR 2.390 DOC ID: COLR Clinton I Rev. 6 Clinton Reload 13 Non-Proprietary Information -Class I (Public)0000-01 27-2434-FBIR-NP Revision 0 Important Notice Regarding Contents of This Report Please Read Carefully This report was prepared by Global Nuclear Fuel -Americas, LLC (GNF-A) solely for use by Exelon ("Recipient") in support of the operating license for Clinton (the "Nuclear Plant"). The information contained in this report (the "Information") is believed by GNF-A to be an accurate and true representation of the facts kn'own-by, obtained by or provided to GNF-A at the time this report was prepared.The only undertakings of GNF-A respecting the Information are contained in the contract between Recipient and GNF-A for nuclear fuel and related services for the Nuclear Plant (the "Fuel Contract") and nothing contained in this document shall be construed as amending or modifying the Fuel Contract. The use of the Information for any purpose other than that for which it was intended under the Fuel Contract, is not authorized by GNF-A. In the event of any such unauthorized use, GNF-A neither (a) makes any representation or warranty (either expressed or implied) as to the completeness, accuracy or usefulness of the Information or that such unauthorized use may not infringe privately owned rights, nor (b) assumes any responsibility for liability or damage of any kind which may result from such use of such information. Information Notice This is a non-proprietary version of the document,0000-0127-2434-EBIR-P,, Revision 0, which has the proprietary information removed. Portions of the document that have been removed are indicated by an open and closed bracket as shown here [[ ]J.Page28 of 57 Page 2 Exelon Nuclear -Nuclear Fuels.CLIC14 Core Operating Limits Report Non-Proprietary Information Submitted in Accordance with 10 CFR 2.390 DOC ID: COLR Clinton 1 Rev. 6 Clinton Reload 13 Non-Proprietary Information,-Class I (Public)0000-01 27-2434-FBIR-NP Revision 0 1. Introduction and, Summary This report, which supplements the. Supplemental Reload Licensing Report,. contains .thermal-mechanical linear heat generation rate (LHGR) limits for the GNF-A fuel designs to be:.loaded into-Clinton.Power Station Unit 1 for Cycle 14. These LHGR limits are obtained from thermal-mechanical considerations only. Approved GNF-A calculation models documented in Reference 1 were used in performing this analysis.LHGR limits as a function of exposure for each bundle of the core design are given in Appendix A. The LHGR values provided in Appendix A provide upper and lower exposure dependent LHGR boundaries which envelope the actual gadolinia dependent LHGR limits. The LHGRs reported have been rounded to two places past the decimal.Appendix B contains a description of the fuel bundles. Table B-1 contains a summary of bundle-specific information, and the figures provide the enrichment distribution and gadolinium distribution for the fuel bundles included in this appendix. These bundles have been approved for use under the fuel licensing acceptance criteria of Reference 1.Page 29 of 57 Page 3 Exelon Nuclear -Nuclear Fuels ý, CLIC14 Core Operating Limits Report Non-Proprietary Information Submitted in Accordance with 10 CFR 2.390 DOC iD: COLR Clinton 1 Rev. 6 Clinton Non-:Proprietary Information' -Class I (Public)-0000-0127-2434-FBIR-NP, Revision 0'.Reload 13'2. References

1. General Electric :Siandard Alýplicatidn fdr' Reactor Fuetl, NEDE-2401 1" P-A- 18, U.S.

NEDE-240-11P=A1 8-US, Alril 2011I.April 2011; and the Page 30 of 57 Page 4 Exelon Nuclear -Nuclear Fuels CLI C14 Core Operating Limits Report Non-Proprietary Information Submitted in Accordance with 10 CFR 2.390 DOC ID: COLR Clinton I Rev. 6 Clinton Reload 13 Non-Proprietary Information,. 0000-01 27-2434-FBIR-NP -Class I (Public) Revision 0* ~Appendix .UO 2/Gd Thermal-Mechanical LHGR Limits Bundle Type: GE14-PIOSNAB418-14GZ-120T-150-T6-3027 (GE14C)Bundle Number: 3027 Peak Pellet Exposure 'U0 2'LHGR Limit GWd/MT (GWd/ST) kW/ft 0.00 (0.00) .13.40 16.00 (14.5.1) 13.40 63.50 (57.61) 8.00 70.00 (63.50) 5.00 Peak Pellet Exposure, Most Limiting Gadolinia LHGR Limit'GWd/MT (GWd/ST) kW/ft 0.00 (0.00) 11.76 13.31 (12.08) 11.76 59.76 (54.21) 7.02 66.12 (59.98) 4.39 Bounding gadolinia LHGR limit for all gadolinium concentrations occurring in this bundle design (8.0%,Gd). Page 31 of 57 Page 5 Exelon Nuclear -Nuclear Fuels CLIC14 Core Operating Limits Report Non-Proprietary Information Submitted in Accordance with 10 CFR 2.390 DOC ID' COLR Clinton I Rev. 6 Clinton " Reload 13 Non-Proprietary Information

• --Class I (Public)0000-01 27-2434-FBIR-NP
• .Revision' 0 U0 2/Gd Thermal-Mechanhical LHGR Limits Bundle Type: GE 14-PI OSNAB418-15GZ-120T- 150-T6-3029 (GE 14C)Bundle Number: 3029 Peak Pellet Exposure U0 2 LHGR Limit GWd/MT (GWd/ST) kW/ft '0.00 (0.00) 13.40.'16.00 (14.51) 13.40;63.50 (57.61) 8:00 70.00 (63:50) 5.00 Peak Pellet Exposure Most Limiting Gadolinia LHGR Limit 2 GWd/MT (GWd/ST) kW/ft 0.00(0.00)

'11.76.13.31 (12.08) 11.76, 59.76 (54.21) 7.02 66.12 (59.98) 4.39 2 Bounding gadolinia LHGR limit for all gadolinium* concentrations occurring in this bundle design (8.0% Gd).Page 32 of 57 Page 6 Exelon Nuclear -Nuclear Fuels, CLIC14 Core Operating Limits Report Non-Proprietary Information Submitted in Accordance with 10 CFR 2.390 DOC ID: COLR Clinton I Rev. 6 Clinton Reload 13 Non-Proprietary Information -Class]. (Public)0000-01 27-2434-FBIR-NP Revision 0 UO 2/Gd dTh ermal-Mechan ical LHGR Limits Bundle Type: GE 14-PI OSNAB422-133GZ-7:I20T-150-T6-3031 (GE4C)J)Bundle Number: 3031 Peak Pellet Exposu-re.," " Uz2 LH-GR Limit GWd/MT (GWd/ST) kW/ft 0.00 (0.00) 13.40 16.00 (14.51) 13.40, 63.50 (57.61) 8.00* 70.00 (63.50) 5.00 Peak Pellet Exposure Most Limiting Gadolinia LHGR Limit 3 GWd/MT (GWd/ST) .kW/ft 0.00 (0.00) 11.76 13.31 (12.08) 11:76* 59.76 (54.21) 7.02-66.12 (59.98) 4.39 3 Bounding gadolinia LHGR limit for all gadolinium concentrations occurring in this bundle. design (8.0% Gd).Page 33 of 57 Page 7 Exelon Nuclear -Nuclear Fuels'CLIC14 Core Operating Limits Report Non-Proprietary Information Submitted in Accordance with 10 CFR 2.390 DOC ID: COLR Clinton I Rev. 6 Cliton 13 Reload. 13 Non-Proprietar ' Information .Class;.I (Public)0000-01 27-2434-FBIR-NP Revision 0 UO 2/Gd Thermal-Mecihanical LHGRLimits Bundle Type: GE14-PIOSNABT,22-15GZ-1I20T'150-'T6ý3025 (GEI4C)" Bundle Number: 3025 Peak Pellet Exposure.' UO. u LHGR Limit GWd/MT (GWd/ST) kWift 0.00 (0.00) 13.40 16.00 (14.51) 13140 63.50 (57.61) 8.00 70.00 (63.50) 5.00 Peak Pellet Exposure `Most Limiting GadoIlinia LHGR Limit 4 GWd/MT (GWd/ST) kw/ft 0.00 (0.00) 11.76 13.31 (12.08) 11.76 59.76 (54.21) 7.02 .66.12 (59.98) 4.39 4 Bounding gadolinia LHGR limit for all gadolinium concentrations occurring in this bundle design (8.0% Gd).Page 34 of 57 Page 8 Exelon Nuclear -Nuclear Fuels, CLIC14 Core Operating Limits Report Non-Proprietary Information Submitted in Accordance with 10 CFR 2.390 DOC ID: COLR Clinton 1 Rev. 6 Clinton Reload 13 Non-Proprietary Information -Class I (Public)0000-0127-2434-FBIR-NP. Revision 0 U0 2/Gd Thermal-Mechanical LHGR Limits Bundle Type: GEl 4-P 1OSNAB418.-1 20T- 150-T6ý3240..(GE14C).,,, Bundle Number: 3240 Peak PelletlExposure UO.z LHGRLimit...

GWdIMT (GWd/ST) kW/ft 0.00 (0.00) 13.406 16.00 (14.51) .13.40* 63..50 (57.61) 8.00 70.00 (63.50) 5.00 Peak Pellet Exposure Most Limiting Gadolinia LHGR Limit'GWd/MT (GWd/ST) kW/ft* 0.00 (0.00) , ,, 11.76, 13.31 (12.08) 11.76 59.76 (54.21) '7.02 66.12 (59.98) 4.39 Bounding gadolinia LHGR limit for all gadolinium concentrations.

occurring in this bundle design (8.0% Gd).Page 35 of 57 Page 9 Exelon Nuclear -Nuclear Fuels'CLIC14 Core Operating Limits Report Non-Proprietary Information Submitted in Accordance with 10 CFR 2.390 DOC ID: COLR Clinton I Rev. 6 Clihton"-Reload 13 Non-Proprietary Information -Class l(Public)Y 0000-0127-2434-FBIR-NP Revision 0 U0 2/Gd Thermal-MechaniCael( LHGR Limits Bundle Type: GEI41-Pr'OSOB465O-13GZ-120T- I:50-T6-3243 (GEI°4I)!Bundle Number: 3243 U0 2 LHGR.Li.m it.1 GWdIMT (.GWd/ST) kW/ft Peak Pellet Exposure Most Limiting Gadolinia LHGR Limit GWd/MT (GWd/ST) kW/ft 6 Bounding gadolinia LHGR limit for all gadolinium concentrations occurring in this bundle design [[Page 36 of 57 Page 10 Exelon Nuclear -Nuclear Fuels, CLIC14 Core Operating Limits Report Non-Proprietary Information Submitted in Accordance with 10 CFR 2.390 DOC ID: COLR. Clinton I Rev. 6 Clinton Reload 13 Non-Proprietary Information. -Class I (Public)0000-0127-2434-FBIR-NP Revision 0 U0 2/Gd Thermal-MechanicalLHGR Limits.Bundle Type: GE14-PI0SNAB418-.I5SGZ:i 20T-1I50-T6-3242(GEI.4C) Bundle Number: 3242 Peak Pellet.Exposure. U0 2 ,LHGR Limitf GWd/MT (GWd/ST) .kW/ft 0.00(0.00) 13.40.16.00 (14.51) 1 3.40., 63.50 (57.6i) 8.00.70.00 (63.50) 5.00 Peak Peliet Exposure', ,;Most Limiting Gadolinia LHGR Limit 7 GWd/MT (GWd/ST) kW/ft 0.00(0.00) 11.76 13.31 (12.08) 11..761" .59.76 (54.21) 7.02 66.12 (59.98), 4.39 7 Bounding gadolinia LHGR limit for.all gadolinium concentrations occurring in this bundledesign (8.0% Gd).Page 37 of 57 Page I11 Exelon Nuclear -Nuclear Fuels'CLIC14 Core Operating Limits Report Non-Proprietary Information Submitted in Accordance with 10 CFR 2.390 DOC ID: COLR Clinton 1'ReV. 6 Clinton `Reload 13 Non-Proprietary Information -Class'l (Public)0000-0127-2434-FBIR-NP Revision 0 U0 2/Gd TherhmaI-Me6hn diCaILHGR Limits Bundle Type: GE I4-P l16SNAB422'-tI3GZ-I 20T-I 50=T6L3239 (GE14C)0 Bundle Number: 3239 Peak Pelletf Exposure .Limit GWd/MT (GWd/ST) .kW/ft 0.00 ((9.00) 13.40 16.00 (1.4.51) 13.40 63.50 (57.61) 8.00 70.00 (63.50) 5-.00 Peak Pellet Exposure -Most Limiting Gadolinia-LHGR Limit 8 GWd/MT (GWd/ST) kW/ft 0.00 (0.00) 11.76 13.31 (12:08). 11F.76 59.76.(54221)

• .. o 7.02 66.12 (59.98) -4.3.9'8 Bounding gadolinia LHGR limit for all gadolinium concentrations occ'urring in this bundle design (8.0% Gd).Page 38 of 57 'Page 12 Exelon Nuclear -Nuclear Fuels CLICi4 Core Operating Limits Report Non-Proprietary Information Submitted in Accordance with 10 CFR 2.390 DOC ID: COLR Clinton I Rev. 6 Clinton Reload 13 Non-Proprietary Information,-Class .1 .(Ptiblici 0000-0127-2434-FBIR-NP Revision 0 Reload 13 -Class I (P.6blic)UO 2 Gd :ThermaI-Mec, hanicaI LHGR Limits Bundle Type: GEl 4-PI OSNAB4 8- !.5GZ,.1 2OT,1 50-T6,3241 (GE 14C).Bundle Number: 3241 Peak Pellet Exposure U0 2 LHG.R Limit GWd/MT (GWd/ST) kW/ft 0.00 (0.00) 13.40 16.00(14.51) 13.40 63.50 (57..61) 8.00..70.00 (63.50) 5.00 Peak Pellet Exposure Most Limiting Gadolinia LHGR Limit 9 GWd/MT" (GWd/ST)'

kW/ft 0.00 (0.00) 11.76 13.31 (12.08) 11.76 " 59.76 (54.21). 7.02 66.12 (59.98) 4.39 9 Bounding gadolinia LHGR limit for all gadolinium concentrations occurring in this bundle design (8.0% Gd)'Page 39 of 57 Page 13 Exelon Nuclear -Nuclear Fuels CLIC14 Core Operating Limits Report Non-Proprietary Information Submitted in Accordance with 10 CFR 2.390 DOC ID: COLR Clinton I Rev". 6 Clinton 'Reload 1.3 S, Non-Proprietary Information -Class I (Public)0000-0127-2434-FBIR-NP Revision 0 UO 2 I/Gd Tfiherimal-M-ecfahaical '6 LHGR Limits Bundle Type: GNF2-P IOSG2B402-I5GZ I 20f2ý-I 50-T6-4609" GNF2)Bundle Number: 4009 eeakkPellet Exposure; UO 2 LHGR Limit GWd/MT (GWd/ST)

• kW/ft " Peak Pellet Exposure Most Limiting Gadolinia.

LHGR Limit' .GWd/MT (GWd/ST) -kW/ft]]10 Bounding gadolinia LHGR limit for all gadolinium concentrations occurring in this bundle design [R]I.Page 40 of 57 Page 14 Exelon Nuclear -NuclearFuels CLICi4 Core Operating Limits Report Non-Proprietary Information Submitted in Accordance with 10 CFR 2.390 DOC ID: COLR Clinton 1 Rev. 6 Clinton Reload 13 Non-Proprietary Information 0000-0127-2434-FBIR-NP -Class I (Public) Revision 0 Uo2/Gd Thermal-Mechanical LHGR Limits, Bundle Type: GNF2-P 1OSG2B40 1-15 GZ-I 20T2-1 50-T6-4010 (GNF2)Bundle Number: 4010 Peak Pellet Exposur*e U0, 2 LHGR Limit, GWd/MT (GWd/ST) kW/ft .Peak Pellet Exposure. Most Limiting Gadolinia LHGR Limit" GWd/MT (GWd/ST) kWfft.Bounding gadolinia LHGR limit for all gadolinium concentrations occurring in- this bundle design f[Page 41 of 57 Page 15 Exelon Nuclear -Nuclear Fuels CLIC14 Core Operating Limits Report Non-Proprietary Information Submitted in Accordance with 10 CFR 2.390 DOC ID:'COLR Clinton 1 Rev. 6 Clinton Reload 13* Non-Proprietary Information

• .-Class I-(Public) 0000-0127-2434-FBIR-NP Revision 0 UO 2 1Gd Thermal-Mechanical LHGR Limits Bundle Type: GNF2-P10SG2B402-6 12G7.0-1 20T2-"50-T&-4011 (GNF2)Bundle Number: 4011 Peak Pellet.Exposuire-U0 2 LHGR Limit.GWd/MT (GWd/ST) kW/ftPeak Pellet Exposure Most Limiting Gadolinia LHGR Limit'2 GWd/MT (GWd/ST) kW/ft'a ]12 Bounding gadolinia LHGR limit' for all gadolinium concentrations occurring in this bundle design[Page 42 of 57 Page 16 Exelon Nuclear.-

Nuclear Fuels.CLIC14 Core Operating Limits Report Non-Proprietary Information Submitted in Accordance with 10 CFR 2.390 DOC ID: COLR Clinton I Rev. 6 Clinton Reload 13 Non-Proprietary Information. -Class I (Public) , 0000-0127-2434-FBIR-NP Revision 0 UO 2/Gd Thermal-Mechanical-LHGR Limits Bundle Type: GNF2-P10SG2B402-14GZ-120T2-150-T6-4012 (GNF2)Bundle Number: 4012 Peak Pellei Expoý'ure U02, LHGR Limit GWd/MT (GWd/ST);. kW/ft" Peak Pellet Exposure, Most Limiting Gadolinia LHGR Limit 13 GWd/MT (GWd/ST) kW/ft[[1. .13 Bounding gadolinia LHGR limit for all gadolinium concentrations occurring in. this bundle design [[]] I.. .. ...Page 43 of 57 Page 17 Exelon Nuclear -Nuclear Fuels CLIC14 Core Operating Limits Report Non-Proprietary Information Submitted in Accordance with 10 CFR 2.390 DOC iD:'COLR Clinton 1 Rev. 6 ClintonI Reload 13 Non-Proprietary Information -Class, I (Public) -0000-0127-2434-FBIR-NP Revision 0-Appendix B .Fuel Bundle Information Table B-1 Bundle Specific Information Max Exposure Fuel Bundle ;Enrichment Weight Weight of.UO 2 6fU at tax, Bundle Number (wt% U-235) ;20 0 C GWd/MT'(kg)" (kg) 14 (GWd/ST)GE1 4-P 10SNAB418-14GZ-3027 *[[. .120T-1 50-T6-3027 (GEl 4C)GEl4-PI0SNAB418-15GZ 3 120T-150-T6-3029 (GE14C) 3029 GEl 4-P IOSNAB422-13GZ-120T-150-T6-3031 (GEI4C)GEl4-PIOSNAB422-15GZ-120T-150-T6-3025 (GE14C)GEI4-PIOSNAB418-15GZ-3240 120T-150-T6-3240 (GEI4C) 3240 GE 141-PI OSCOB405-13GZ-120T-150-T6-3243 (GE14I) 3243 GE14-PIOSNAB418-15GZ-120T-150-T6-3242 (GE14C) 3242 GE 14-P 1 OSNAB422-13 GZ-120T-150-T6-3239 (GE14C)GE I4-P1OSNAB418-15GZ-120T-150-T6-3241 (GE14C)GNF2-PI 0SG2B402-15GZ-120T2-150-T6-4009 (GNF2)GNF2-P I 0SG2B401-15GZ-120T2-150-T6-4010 (GNF2)GNF2-P IOSG2B402-12G7.0-4011 120T2-150-T6-4011 (GNF2)GNF2-P 10SG2B402-14GZ-120T2-150-T6-4012 (GNF2)14 Maximum lattice k. for the most reactive uncontrolled state plus a [[]] adder for uncertainties. Page 44 of 57 Page 18 Exelon Nuclear -Nuclear Fuels CLI C14 Core Operating Limits Report Non-Proprietary Information Submitted in Accordance with 10 CFR 2.390 DOC, ID: COLR Clinton 1 Rev. 6 Clinton Reload 13 Non-Proprietary Information -Class I (Public). , 0000-01 27-2434-FBIR-NP Revision 0 Reload 13[[Figure B-i Enrichment and Gadolinium Distiribution for EDB No. 3027 Fuel Bundle GEi4-PIOSNAB418-I4GZ-'120T-"150-T6-3027 (CE14C)Page 45 of 57 Page 19 Exelon Nuclear -'Nuclear Fuels : CLIC14 Core Operating Limits Report Non-Proprietary Information Submitted in Accordance with 10 CFR 2.390 DOC ID: COLR Clinton 'I Rev. 6 Clinton'Reload 13-" Non-Proprietary Information -Class:I (Public)0000-0127-2434-FBIR-NP Revision 0[II Figure B-2 Enrichment and Gadolinium Distribution for EDB No. 3029 Fuel Bundle GEI4-PIOSNAB418-15GZ-120T-150-T6-3029 (GEI4C)Page 46 of 57 Page 20 b Exelon Nuclear -Nuclear Fuels CLIC14 Core Operating Limits Report Non-Proprietary Information Submitted in Accordance with 10 CFR 2.390 DO C,ID: COLR.Clinton 1 Rev. 6 Clinton Reload 13 Non-Proprietary Information 0000-01 27-2434-FBIR-NP -(lass l (PiihlicV Revision 0 Reload 13 -Class I (Public) Revision 0[[I Figure B-3 Enrichment and Gadolinium. Distributionw for EDB No..3031 Fuel'Bundle GEI4-PIOSNAB422-13GZ-120T4150-T6-3031 (GE14C)Page 47 of 57 Page 21 Exelon Nuclear -Nuclear Fuels CLIC14 Core Operating Limits Report Non-Proprietary Information Submitted in Accordance with 10 CFR 2.390 DOC ID: COLR Clinton 1 Rev. 6 Clinton Reload 13 Non-Proprietary Information .Class.i (Public)0000-01 27-2434-FBIR-NP Revision 0[[I I]Figure t-4 Enrichment and Gadolinium'Distribution for EDBNo. 3025' Fuel Bundle GE.1'4-PIOSNAB422-15GZJ120T:150:T6:3025 (GE14C)Page 48 of 57 Page 22 Exelon Nuclear -Nuclear Fuels CLIC14 Core Operating Limits Report Non-Proprietary Information Submitted in Accordance with 10 CFR 2.390 DOC ID:. COLR Clinton I Rev. 6 Clinton Reload 13 Non-Proprietary Information -Class I (Public ) , 0000-01 27-2434-FBIR-NP Revision 0 1[, FigureB-5 Enrichment and Gadolinium Distribution for EDB No. 3240 Fuel ,Bundle GEI4-PIOSNAB418-15GZ-1.20T-150TT6-324O (G E14C)Page 49,of 57P, Page 23 Exelon Nuclear -Nuclear Fuels CLIC14 Core Operating Limits Report Non-Proprietary Information Submitted in Accordance with 10 CFR 2.390 DOC IDM COLR Clinton I Rev. 6 Clinton. Non-Proprietary Information Reload 13 -ClassI.I(Public). " " 0000-01 27-2434-FBIR-NP Revision'O [[Figure B-6 Enrichment and Gadolinium Distribution for EDB No. 3243 Fuel Bundlie'dEIIP10s-OCOB405-13GZ-120T-150-T6-3243 (GEI41)Page 50"of 57 Page 24 Exelon Nuclear -NuclearFuels CLIC14 Core Operating Limits Report Non-Proprietary Information Submitted in Accordance with 10 CFR 2.390 DOC ID: COLR Clinton I Rev. 6 Clinton Reload 13 Non-Proprietary Information -Class-! (Public), 0000-01 27-2434-FBIR-NP Revision 0[r FigureB-7 Enrichment and Gadolinium.Distribution, for EDB No. 3242 Fuel Bundle GEI4-PIOSNAB418-15GZ-120T-150-T6-3242 (GE14C)Page 51 of 57 Page 25 Exelon Nuclear -Nuclear Fuels: CLIC14 Core Operating Limits Report Non-Proprietary Information Submitted in Accordance with 10 CFR 2.390 DOC ID: COLR Clinton 1 Rev. 6 Clinton Rolnawi 1 q Non-Proprietary Information -Class-I (Public), .0000-01 27-2434-FBIR-NP Revision 0 Reload 13[[Figure.B-8 Enrichment and Gadolinium Distribution for EDB.No.:3239 Fuel Bun'dle GE14-P1OSNAB422-13GZ-120T-150-T6-3239 (GEl4C)Page 52 of 57 Page 26 Exelon Nuclear -Nuclear Fuels CLIC14 Core Operating Limits Report Non-Proprietary Information Submitted in Accordance with 10 CFR 2.390 DOC ID: COLR Clinton I Rev. 6 Clinton R plnntl 1"l Non-Proprietary Information -Class I,(Public), 0000-01 27-2434-FBIR-NP Revision 0 R-1-1 11 1[Figure B-9 Enrichment and Gadolinium Distribution for EDB No. 3241 Fuel Bundle GE14-PIOSNAB418-15GZ-120T-150-T6-3241 (GEI4C)Page 53 of 57 Page 27 aL Exelon Nuclear -Nuclear Fuels -CLIC14 Core Operating Limits Report Non-Proprietary Information Submitted in Accordance with 10 CFR 2.390 DOC ID: COLR Clinton I Rev. 6 Clinton Reload 1-3 Non-Proprietary Information -Class:l(Public). 0000-0127-2434-FBIR-NP Revision 0'Figure B-10 Enrichment and Gadolinium Distribution for EDB No. 4009 Fuel Bundle GNF2-PIOSG2B402-15GZ-120T2-150-T6-4009 (GNF2)Page 54 of 57 Page 28 a 1.Exelon Nuclear -NuclearFuels CLIC14 Core Operating Limits Report Non-Proprietary Information Submitted in Accordance with 10 CFR 2.390 DOC ID: COLR Clinton 1 Rev. 6 Clinton.Reload 13 Non-Proprietary Information. 0000-0127-2434-FBIR-NP -Class I (Public) Revision 0 Figure B_11 Enrichment and Gadolinium Distribution for EDB No. 4010' Fuel Bundle GNF2-PIOSG2B401-15GZ-120T2-150-T6-4010 (GNF2)Page 55 of057 Page 29 Exelon Nuclear -Nuclear Fuels CLIC14 Core Operating Limits Report Non-Proprietary Information Submitted in Accordance with 10 CFR 2.390 DOC 'ID: COLR Clinton I Rev. '6 Clinton : Reload 13 Non-Proprietary Information -Class§1(Public) '0000-0127-2434-FBIR-NP Revision 0 Figure B-12 Enrichmentand Gadolinium Distribution for EDB No. 4011 Fuel Bundle GNF2-P10SG2B402-12G7.0-120T2-I50-T6-40.11 (GNF2)Page 56 of 57 Page 30 Exelon Nuclear -Nuclear Fuels CLIC14 Core Operating Limits Report Non-Proprietary Information Submitted in Accordance with 10 CFR 2.390 DOC ID: COLR Clinton I Rev. 6 Clinton Reloaid 1 l Non-Proprietary Information -Class I (Public)0000-01 27-2434-FBIR-NP Revision 0 Reload 13[[I Figure B-13 Enrichment and Gadolinium Distribution for EDB No. 4012 Fuel Bundle GNF2-P1OSG2B402-14GZ-120T2-150-T6-4012 (GNF2)Page 57 of 57 Page 31}}