ML15069A045

Clinton Power Station, Unit 1, Core Operating Limits Report Cycle 15, Revision 9

ML15069A045
Person / Time
Site:	Clinton
Issue date:	02/27/2015
From:	Exelon Generation Co
To:	Office of Nuclear Reactor Regulation
References
U-604201
Download: ML15069A045 (62)

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. ATTACHMENT 2Core Operating Limits Report for Clinton Power Station Unit 1, Cycle 15,Revision 9(Non-Proprietary Version)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. Global Nuclear Fuel -AmericasAFFIDAVIT I, Lukas Trosman, state as follows:(1) I am Engineering

Manager, Reload Design and Analysis, Global Nuclear Fuel -Americas, LLC (GNF-A),

and have been delegated the function of reviewing the information described in paragraph (2) which is sought to be withheld, and have been authorized toapply for its withholding. (2) The information sought to be withheld is contained in GNF-A proprietary report0000-01 54-8722-FBIR-P, Fuel Bundle Information Report for Clinton Power Station Unit 1Reload 14 Cycle 15, Revision 0, August 2013. GNF-A proprietary information in0000-01 54-8722-FBIR-P, Fuel Bundle Infornmation Report for Clinton Power Station Unit 1Reload 14 Cycle 15, Revision 0, August 2013 is identified by a dotted underline insidedouble square brackets. [[This ".se..entence --.is --.an ..exampl.e... 3]] Figures and large equationobjects are identified with double square brackets before and after the object. In each case,the superscript notation f3l refers to Paragraph (3) of this affidavit, which provides the basisfor the proprietary determination. (3) In making this application for withholding of proprietary information of which it is theowner or licensee, GNF-A relies upon the exemption from disclosure set forth in theFreedom of Information Act ("FOIA"), 5 USC Sec. 552(b)(4), and the Trade Secrets Act,18 USC Sec. 1905, and NRC regulations 10 CFR 9.17(a)(4), and 2.390(a)(4) for "tradesecrets" (Exemption 4). The material for which exemption from disclosure is here soughtalso qualify under the narrower definition of "trade secret", within the meanings assigned tothose terms for purposes of FOIA Exemption 4 in, respectively, Critical Mass EnergyProject v. Nuclear Regulatory Commission, 975 F2d 871 (DC Cir. 1992), and PublicCitizen Health Research Group v. FDA, 704 F2d 1280 (DC Cir. 1983).(4) Some examples of categories of information which fit into the definition of proprietary information are:a. Information that discloses a process, method, or apparatus, including supporting dataand analyses, where prevention of its use by GNF-A's competitors without licensefrom GNF-A constitutes a competitive economic advantage over other companies;

b. Information which, if used by a competitor, would reduce his expenditure of resources or improve his competitive position in the design, manufacture,

shipment, installation, assurance of quality, or licensing of a similar product;c. Information which reveals aspects of past, present, or future GNF-A customer-funded development plans and programs, resulting in potential products to GNF-A;d. Information which discloses patentable subject matter for which it may be desirable toobtain patent protection.

0000-01 54-8722-FBIR-P Affidavit Page I of 3 The information sought to be withheld is considered to be proprietaly for the reasons setforth in paragraphs (4)a. and (4)b. above.(5) To address 10 CFR 2.390 (b) (4), the information sought to be withheld is being submitted to NRC in confidence. The information is of a sort customarily held in confidence by GNF-A, and is in fact so held. The information sought to be withheld has, to the best of myknowledge and belief, consistently been held in confidence by GNF-A, no public disclosure has been made, and it is not available in public sources. All disclosures to third partiesincluding any required transmittals to NRC, have been made, or must be made, pursuant toregulatory provisions or proprietary agreements which provide for maintenance of theinformation in confidence. Its initial designation as proprietary information, and thesubsequent steps taken to prevent its unauthorized disclosure, are as set forth in paragraphs (6) and (7) following. (6) Initial approval of proprietary treatment of a document is made by the manager of theoriginating component, the person most likely to be acquainted with the value andsensitivity of the information in relation to industry knowledge, or subject to the termsunder which it was licensed to GNF-A. Access to such documents within GNF-A is limitedon a "need to know" basis.(7) The procedure for approval of external release of such a document typically requires reviewby the staff manager, project manager, principal scientist or other equivalent authority, bythe manager of the cognizant marketing function (or his delegate), and by the LegalOperation, for technical

content, competitive effect, and determination of the accuracy ofthe proprietary designation.

Disclosures outside GNF-A are limited to regulatory bodies,customers, and potential customers, and their agents, suppliers, and licensees, and otherswith a legitimate need for the information, and then only in accordance with appropriate regulatory provisions or proprietary agreements. (8) The information identified in paragraph (2) is classified as proprietary because it containsdetails of GNF-A's fuel design and licensing methodology. The development of thismethodology, along with the testing, development and approval was achieved at asignificant cost to GNF-A.The development of the fuel design and licensing methodology along with the interpretation and application of the analytical results is derived from an extensive experience databasethat constitutes a major GNF-A asset.(9) Public disclosure of the information sought to be withheld is likely to cause substantial harm to GNF-A's competitive position and foreclose or reduce the availability of profit-making opportunities. The information is part of GNF-A's comprehensive BWR safety andtechnology base, and its commercial value extends beyond the original development cost.The value of the technology base goes beyond the extensive physical database andanalytical methodology and includes development of the expertise to determine and applythe appropriate evaluation process. In addition, the technology base includes the valuederived from providing analyses done with NRC-approved methods.0000-01 54-8722-FBIR-P Affidavit Page 2 of 3 The research, development, engineering, analytical, and NRC review costs comprise asubstantial investment of time and money by GNF-A.The precise value of the expertise to devise an evaluation process and apply the correctanalytical methodology is difficult to quantify, but it clearly is substantial. GNF-A's competitive advantage will be lost if its competitors are able to use the results ofthe GNF-A experience to normalize or verify their own process or if they are able to claiman equivalent understanding by demonstrating that they can arrive at the same or similarconclusions. The value of this information to GNF-A would be lost if the information were disclosed tothe public. Making such information available to competitors without their having beenrequired to undertake a similar expenditure of resources would unfairly provide competitors with a windfall, and deprive GNF-A of the opportunity to exercise its competitive advantage to seek an adequate return on its large investment in developing and obtaining these very valuable analytical tools.I declare under penalty of perjury that the foregoing affidavit and the matters stated therein aretrue and correct to the best of my knowledge, information, and belief.Executed on this 27th day of August 2013.Lukas TrosmanEngineering

Manager, Reload Design and AnalysisGlobal.Nuclear Fuel -Americas, LLC0000-01 54-8722-FBIR-P Affidavit Page 3 of 3 Exelon Nuclear-Nutclear Fuels DOC M: COLR Clinton i Rev. 9CLICIS Core Operating Lmits ReportNon-PmrupdUy InknmaUan Submfbd inArrdance Wth IOCFR 2.300CORE OPERATING LIMITS REPORT:FORCLINTON POWER STATION UNIT I CYCLE IS:PreparedReviewedReviewedReviewedApprovedStation QLReviewerBy.:K~lstin C. M&Gskey..

RE Riew.o- .oi. G: ..:i.. .H. ou.g .al .By:By:independent Reviewer-FrPk W. Trikurc.ir7;B.mDDat: a.- LIIDate. 9iDate: z/a /,-,Date:____ Date: 21Date:tI "By*i-9F Manager-James J. TusarPage I of 58 Exelon Nuclear -Nuclear Fuels DOC ID: COLR Clinton 1 Rev. 9CLIC15 Core Operating Limits ReportNon-Proprietary Information Submitted inAccordance with 10 CFR 2.390Table of Contents1.0 Terms and Definitions 52.0 General Information 73.0 MAPLHGR Limits 84.0 MCPR Limits 105.0 Linear Heat Generation Rate Limits 176.0 Reactor Protection System (RPS) Instrumentation 237.0 Turbine Bypass System Parameters 238.0 Stability Protection Setpoints 249.0 Modes of Operation 2510.0 Methodology 2611.0 References 26Appendix A 27Page 2 of 58 Exelon Nuclear -Nuclear Fuels DOC ID: COLR Clinton I Rev. 9CLIC15 Core Operating Limits ReportNon-Proprietary Information Submitted inAccordance with 10 CFR 2.390List of TablesPageTable 3-1 MAPLHGR Versus Average Planar Exposure -GE14C/GE141 8Table 3-2 MAPLHGR Versus Average Planar Exposure -GNF2 8Table 3-3 MAPLHGR Single Loop Operation (SLO) Multiplier 9Table 3-4 MAPLHGR Multiplier for Loss of'FULL' Feedwater Heating 9Table 4-1 Operating Limit Minimum Critical Power Ratio 12Table 4-2 Power Dependent MCPR Limits MCPR(P) and Multipliers K(P) 13Table 4-3 PROOS Power Dependent MCPR Limits MCPR(P) and Multipliers K(P) 14Table 4-4 Dual Loop Operation (DLO) Flow Dependent MCPR Limits MCPR(F) 15for Base Case/PROOS Table 4-5 Single Loop Operation (SLO) Flow Dependent MCPR Limits MCPR(F) 15for Base Case/PROOS Table 4-6 Dual Loop Operation (DLO) Flow Dependent MCPR Limits MCPR(F) 16for Two or More TBVOOSTable 4-7 Single Loop Operation (SLO) Flow Dependent MCPR Limits MCPR(F) 16for Two or More TBVOOSTable 5-1 Linear Heat Generation Rate Limits for U02 Rods 18Table 5-2 Linear Heat Generation Rate Limits for Gad Rods 18Table 5-3 Power Dependent LHGR Multiplier LHGRFAC(P) 19Table 5-4 Flow Dependent LHGR Multiplier LHGRFAC(F) for Base Case/PROOS 20Table 5-5 Flow Dependent LHGR Multiplier LHGRFAC(F) for Two or More TBVOOS 20Table 5-6 LHGR Single Loop Operation (SLO) Reduction Factor 20Page 3 of 58 Exelon Nuclear -Nuclear Fuels DOC ID: COLR Clinton 1 Rev. 9CLI C15 Core Operating Limits ReportNon-Proprietary Information Submitted inAccordance with 10 CFR 2.390Table 5-7 Power Dependent LHGR Multiplier LHGRFAC(P) (Loss of'FULL' 21Feedwater 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 Two or More TBVOOS 22(Loss of 'FULL' Feedwater Heating)Table 7-1 Reactor Power Limitation -Turbine Bypass Valves Out of Service 23Table 8-1 OPRM PBDA Trip Setpoints 24Table 8-2 OPRM PBDA Trip Setpoints -SLO 24Table 9-1 Modes of Operation 25Page 4 of 58 Exelon Nuclear -Nuclear FuelsCLIC15 Core Operating Limits ReportNon-Proprietary Information Submitted inAccordance with 10 CFR 2.3901.0 Terms and Definitions DOC ID: COLR Clinton 1 Rev. 9ADSOOSBase CaseCoastdown DLOFFWTRFWHOOSICFLHGRLHGRFAC(F) LHGRFAC(P) MAPLHGRMCPRMCPR(F)MCPR(P)MELLLAMSIVOLMCPROPRMPROOSAutomatic Depressurization System Valve Out of ServiceA case analyzed with two (2) Safety-Relief Valves Out-of-Service (OOS), one (1)Automatic Depressurization System valve OOS, one (1) Turbine Control Valve stuckclosed, one (1) Turbine Stop Valve stuck closed, one (1) Turbine Bypass ValveOOS, and up to a 50°F feedwater temperature reduction (FWTR includes feedwater heater OOS or final feedwater temperature reduction) at any point in the cycleoperation in Dual Loop mode (Reference 3).The reactor condition where thermal 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 andICF.Dual Reactor Recirculation Loop Operation Final Feedwater Temperature Reduction Feedwater Heaters Out of ServiceIncreased Core FlowLinear Heat Generation RateLHGR thermal limit flow dependent multipliers LHGR thermal limit power dependent multipliers Maximum Average Planar Linear Heat Generation RateMinimum Critical Power RatioMCPR thermal limit flow dependent adjustments and multipliers MCPR thermal limit power dependent adjustments and multipliers Maximum Extended Load Line Limit AnalysisMain Steam Isolation ValveOperating Limit Minimum Critical Power RatioOscillation Power Range MonitorPressure Regulator Out of ServicePage 5 of 58 Exelon Nuclear -Nuclear Fuels DOC ID: COLR Clinton 1 Rev. 9CLLC15 Core Operating Limits ReportNon-Proprietary Information Submitted inAccordance with 10 CFR 2.390SLO Single Reactor Recirculation Loop Operation SRVOOS Safety Relief Valve Out of ServiceTBVOOS Turbine Bypass Valve(s) Out of Service -valves are not credited for fast opening or fornormal pressure controlTCV Turbine Control ValveTSV Turbine Stop ValvePage 6 of 58 Exelon Nuclear -Nuclear Fuels DOC ID: COLR Clinton I Rev. 9CLIC15 Core Operating Limits ReportNon-Proprietary Information Submitted inAccordance with 10 CFR 2.3902.0 General Information This report is prepared in accordance with Technical Specification 5.6.5 of Reference

1. Power and flowdependent limits and multipliers are listed for various power and flow levels. Linear interpolation is tobe used to find intermediate values.These values have been determined using NRC-approved methodologies presented in Section 10 and areestablished 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 to 99% of rated core flow during full power operation
• Increased Core Flow (ICF) up to 107% of rated core flow* Final Feedwater Temperature Reduction (FFWTR) up to 50°F during cycle extension operation
• Feedwater Heater Out of Service (FWHOOS) up to 50°F feedwater temperature reduction atany time during the cycle prior to cycle extension.

Page 7 of 58 Exelon Nuclear -Nuclear FuelsCLLC15 Core Operating Limits ReportNon-Proprietary Information Submitted inAccordance with 10 CFR 2.390DOC ID: COLR Clinton 1 Rev. 93.0 MAPLHGR Limits3.0 Technical Specification

Reference:

Sections 3.2.1 and 3.4.1.3.1

Description:

Table 3-1 is used to determine the maximum average planar linear heat generation rate (MAPLHGR) limit for GE14C and GE141 fuel. Table 3-2 is used to determine the maximum average planar linear heatgeneration rate (MAPLHGR) limit for GNF2 fuel. Limits listed in Table 3-1 and Table 3-2 are for dualreactor recirculation loop operation (DLO).For single reactor recirculation loop operation (SLO), the MAPLHGR limits given in Table 3-1 andTable 3-2 must be multiplied by a SLO MAPLHGR multiplier provided in Table 3-3. The SLOMAPLHGR multiplier for all fuel types is 0.76 (Reference 3).For Loss of 'FULL' Feedwater Heating (+/-10 'F outside design NORMAL temperature, meaningchanges in feedwater temperature greater than 10 0F and less than or equal to 50 TF), the MAPLHGR limitsgiven in Table 3-1 and 3-2 must be multiplied by a LHGR multiplier provided in Table 3-4. The Loss of'FULL' Feedwater Heating LHGR multiplier for all fuel types is 0.99 (Reference 7).Table 3-1MAPLHGR Versus Average Planar Exposure -GE14C/GE1411 (Reference 3)Avg. Planar Exposure MAPLHGR Limit(GWd/ST) (kW/ft)0.00 12.8219.13 12.8257.61 8.0063.50 5.00Table 3-2MAPLHGR Versus Average Planar Exposure -GNF21(Reference 3)Avg. Planar Exposure MAPLHGR Limit(GWd/ST) (kW/ft)0.00 13.7817.15 13.7860.78 6.8763.50 5.50Linear interpolation should be used for points not listed in the table.Page 8 of 58 Exelon Nuclear -Nuclear FuelsCLI C15 Core Operating Limits ReportNon-Proprietary Information Submitted inAccordance with 10 CFR 2.390DOC ID: COLR Clinton I Rev. 9Table 3-3MAPLHGR Single Loop Operation (SLO) Multiplier (Reference 3)Fuel MAPLHGRType SLO Multiplier All Fuel Types 0.760Table 3-4MAPLHGR Multiplier for Loss of 'FULL' Feedwater Heating(Reference 7)FuelTypeMAPLHGRMultiplier All Fuel Types 0.990Page 9 of 58 Exelon Nuclear -Nuclear Fuels DOC ID: COLR Clinton I Rev. 9CLIC15 Core Operating Limits ReportNon-Proprietary Information Submitted inAccordance with 10 CFR 2.3904.0 MCPR Limits4.0 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 LimitsThe 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 MCPRFor 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 lessthan 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 afunction 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 4-2or Table 4-3.4.1.1.2 Flow-Dependent MCPRTables 4-4 through 4-7 give the MCPR(F) as a function of flow based on the applicable plantcondition. The limits for dual loop operation are listed in Tables 4-4 and 4-6. The limits forsingle loop operation are listed in Tables 4-5 and 4-7. The MCPR(F) determined from thesetables is the flow dependent OLMCPR.4.1.2 Automatic Flow Control MCPR LimitsAutomatic Flow Control MCPR Limits are not provided. Page 10 of 58 Exelon Nuclear -Nuclear Fuels DOC ID: COLR Clinton I Rev. 9CLIC15 Core Operating Limits ReportNon-Proprietary Information Submitted inAccordance with 10 CFR 2.3904.1.3 Option A and Option BOption 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. Reload...analyses performed by GNF for Cycle 15 Option A MCPR limits utilized a 20% core averageinsertion 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 averagescram insertion time does not meet the Option B criteria, the appropriate MCPR value maybe determined from a linear interpolation between the Option A and B limits as specified byequation 4 in Reference 5 Section 4.4.1.4 Recirculation Flow Control Valve SettingsCycle 15 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 allrunout events (Reference 3).Page II of 58 Exelon Nuclear -Nuclear Fuels DOC ID: COLR Clinton I Rev. 9CLIC15 Core Operating Limits ReportNon-Proprietary Information Submitted inAccordance with 10 CFR 2.390Table 4-1Operating Limit Minimum Critical Power Ratio(Reference 3)GE14C and GNF2 GE14C and GNF2EOOS Fuel2 Option A Fuel2 Option BCombination All Exposures All Exposures Base Case 1.431 1.431DLO4 1.431 1.431Base CaseSL03.4 1.43 1.43PROOSDPOS4 1.431 1.431PROOSSLO3,4 1.43 1.43Two or More 1TBVOOS DLOTwo or MoreTBVOOS SLO3 1.46 1.43Notes for Table 4-1:1. Value is adjusted to obtain an OPRM amplitude setpoint of 1.10.2. GE141 OLMCPR is the GE14C OLMCPR shown plus 0.07, per Reference 3.3. SLO Option A(B) OLMCPR is the transient DLO Option A(B) OLMCPR plus 0.03 or the OPRM OLMCPRvalue, whichever is highest.4. Includes TCV and/or TSV stuck closed, 1 TBVOOS.Page 12 of 58 Exelon Nuclear -Nuclear FuelsCLI C15 Core Operating Limits ReportNon-Proprietary Information Submitted inAccordance with 10 CFR 2.390DOC ID: COLR Clinton I Rev. 9Table 4-2Power Dependent MCPR Limits MCPR(P) and Multipliers K(P)1'2(References 3 and 9)EQOS Core Flow Core Thermal Power (%)E C(% of 0.0 121.6 1<33.3 >33.3 <70.0 1P>70.0 100.0Rated) MCPR(P) K(P)Base Case4 DLO :< 50 2.31 2.31 2.10GNF2/GE14C 3 1.351 1.212 1.163 1.000Option A > 50 2.46 2.46 2.17Base Case4 DLO <50 2.31 2.31 2.10GNF2/GE14C 1.228 1.102 1.057 1.000Option B5 > 50 2.46 2.46 2.17Base Case4 DLO <50 2.38 2.38 2.17GE141 1.234 1.107 1.062 1.000Option B5 > 50 2.53 2.53 2.24Base Case4 SLO <50 2.34 2.34 2.13GNF2/GE14C 3 1.351 1.212 1.163 1.000Option A/B > 50 2.49 2.49 2.20Two or More <50 2.31 2.31 2.10TBVOOS DLOGNF2/GE14C3 1.351 1.212 1.163 1.000Option A/B > 50 2.46 2.46 2.17Two or More < 50 2.34 2.34 2.13TBVOOS SLO 1GNF2/GE14C3 1.351 1.212 1.163 1.000Option A/B > 50 2.49 2.49 2.20Notes for Table 4-2:1. Values are interpolated between relevant power levels.2. Allowable EOOS conditions are listed in Section 9.0.3. An adder of 0.07 is applied to the GE14C MCPR(P) values for GE141, per Reference

3. GE14C MCPR(P)limits are bounding for GNF2.4. Includes TCV and/or TSV stuck closed, 1 TBVOOS.5. These values are only valid for a stability OLMCPR of 1.43 for GNF2 and GE14C and 1.50 for GE141 withOption B Scram Times.Page 13 of 58 Exelon Nuclear -Nuclear FuelsCLI C15 Core Operating Limits ReportNon-Proprietary Information Submitted inAccordance with 10 CFR 2.390DOC ID: COLR Clinton 1 Rev. 9Table 4-3PROOS Power Dependent MCPR Limits MCPR(P) and Multipliers K(P)1'2(References 3 and 9)EQOS Core Core Thermal Power (%)Combination

-(% 33.3 60.0 <85.0 >85.0of Rated) MCPR(P) K(P)PROOS4 DLO < 50 2.31 2.31 2.10GNF2/GE14C 3 1.558 1.436 1.309 1.084 1.000Option A > 50 2.46 2.46 2.17PROOS4 DLO < 50 2.31 2.31 2.10GNF2/GE14C 1.416 1.305 1.190 1.0296 1.000Option B5 > 50 2.46 2.46 2.17PROOS4 DLO < 50 2.38 2.38 2.17GE141 1.423 1.312 1.196 1.0316 1.000Option B > 50 2.53 2.53 2.24PROOS4 SLO <50 2.34 2.34 2.13GNF2/GE14C 3 1.558 1.436 1.309 1.084 1.000Option A/B > 50 2.49 2.49 2.20Notes for Table 4-3:1. Values are interpolated between relevant power levels.2. Allowable EOOS conditions are listed in Section 9.0.3. An adder of 0.07 is applied to the GE14C MCPR(P) values for GE141, per Reference

3. GE14C MCPR(P)limits are bounding for GNF2.4. Includes TCV and/or TSV stuck closed, 1 TBVOOS.5. These values are only valid for a stability OLMCPR of 1.43 for GNF2 and GE14C and 1.50 for GE141 withOption B Scram Times.6. Base Case K(P) is bounding and was interpolated for PROOS.Page 14 of 58 Exelon Nuclear -Nuclear FuelsCLI C15 Core Operating Limits ReportNon-Proprietary Information Submitted inAccordance with 10 CFR 2.390DOC ID: COLR Clinton 1 Rev. 9Table 4-4Dual Loop Operation (DLO) Flow Dependent MCPR Limits MCPR(F) for Base Case/PROOS' (Reference 3)Core Flow MCPR(F) MCPR(F)(% rated) GNF2/GE14C GE1410.0 1.88 1.9525.0 1.70 1.7784.1 1.27 _93.7 -1.27109.0 1.27 1.27Table 4-5Single 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 GE1410.0 1.91 1.9825.0 1.73 1.8084.1 1.30 _93.7 -1.30109.0 1.30 1.30Linear interpolation should be used for points not listed in the table.Page 15 of 58 Exelon Nuclear -Nuclear FuelsCLIC15 Core Operating Limits ReportNon-Proprietary Information Submitted inAccordance with 10 CFR 2.390DOC ID: COLR Clinton 1 Rev. 9Table 4-6Dual Loop Operation (DLO) Flow Dependent MCPR Limits MCPR(F) for Two or More TBVOOS1(Reference 3)Core Flow MCPR(F) MCPR(F)(% rated) GNF2/GE14C GE1410.0 2.04 2.1125.0 1.85 1.92100.0 1.27 _109.0 1.27 1.27Table 4-7Single Loop Operation (SLO) Flow Dependent MCPR Limits MCPR(F) for Two or More TBVOOS1(Reference 3)Core Flow MCPR(F) MCPR(F)(% rated) GNF2/GE14C GE1410.0 2.07 2.1425.0 1.88 1.95100.0 1.30 j109.0 1.30 1.30Linear interpolation should be used for points not listed in the table.Page 16 of 58 Exelon Nuclear -Nuclear Fuels DOC ID: COLR Clinton 1 Rev. 9CLIC15 Core Operating Limits ReportNon-Proprietary Information Submitted inAccordance with 10 CFR 2.3905.0 Linear Heat Generation Rate Limits5.1 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: thepower dependent LHGR Factor, LHGRFAC(P), the flow dependent LHGR Factor, LHGRFAC(F), orthe 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 plantconditions. The SLO multiplication factor can be found in Table 5-6. Tables 5-1 and 5-2 are theLHGR 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. Themost limiting values are provided here as a convenience and do not imply that all the Gadolinia fuelrods must satisfy the listed values.For Loss of 'FULL' Feedwater Heating (+/-10 OF outside design NORMAL temperature, meaningchanges in feedwater temperature greater than 10 OF and less than or equal to 50 OF), 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 beenevaluated and thus is not a valid operating mode. (Reference 8)Page 17 of 58 Exelon Nuclear -Nuclear FuelsCLI C15 Core Operating Limits ReportNon-Proprietary Information Submitted inAccordance with 10 CFR 2.390DOC ID: COLR Clinton 1 Rev. 9Table 5-1Linear Heat Generation Rate Limits for U02 Rods1(Reference 4)Fuel Type LHGR LimitGNF2 See Appendix AGE14C See Appendix AGE141 See Appendix ATable 5-2Linear Heat Generation Rate Limits for Gad Rods1(Reference 4)Fuel Type LHGR LimitGNF2 See Appendix AGE14C See Appendix AGE141 See Appendix ALinear interpolation should be used for points not listed in the table.Page 18 of 58 Exelon Nuclear -Nuclear Fuels DOC ID: COLR Clinton 1 Rev. 9CLIC15 Core Operating Limits ReportNon-Proprietary Information Submitted inAccordance with 10 CFR 2.390Table 5-3Power Dependent LHGR Multiplier LHGRFAC(P) 2(Reference 3)Core Thermal Power (%)CoreEOOS FlowCo on Flof 0.0 21.6 <33.3 >33.3 40.0 <60.0 >60.0 100.0Combination (% ofRated) _ L_ _ __LHGRFAC(P) Base Case1 < 50 0.634 0.634 0.6890.651 ---1.000DLO/SLO > 50 0.572 0.572 0.600Two or More < 50 0.634 0.634 0.689TBVOOS 0.651 ---1.000DLO/SLO > 50 0.572 0.572 0.600PROOS1 < 50 0.560 0.560 0.5600.560 0.560 0.709 0.749 1.000DLO/SLO > 50 0.560 0.560 0.560Notes 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 58 Exelon Nuclear -Nuclear FuelsCLI C15 Core Operating Limits ReportNon-Proprietary Information Submitted inAccordance with 10 CFR 2.390DOC ID: COLR Clinton 1 Rev. 9Table 5-4Flow Dependent LHGR Multiplier LHGRFAC(F) for Base Case/PROOS 1(Reference 3)Core Flow LHGRFA(% rated)0.0 0.44225.0 0.61230.0 0.64682.2 1.000109.0 1.000Table 5-5Flow Dependent LHGR Multiplier LHGRFAC(F) for Two or More TBVOOS1(Reference 3)Core Flow LHGRFAC(F) (% rated)0.0 0.14025.0 0.36530.0 0.41040.0 0.50050.0 0.63080.0 0.86098.3 1.000109.0 1.000Table 5-6LHGR Single Loop Operation (SLO) Reduction Factor(Reference 3)LHGRFuelSLType SLOType Multiplier All Fuel Types 0.7601 Linear interpolation should be used for points not listed in the table.Page 20 of 58 Exelon Nuclear -Nuclear FuelsCLIC15 Core Operating Limits ReportNon-Proprietary Information Submitted InAccordance with 10 CFR 2.390DOC ID: COLR Clinton I Rev. 9Table 5-7Power Dependent LHGR Multiplier LHGRFAC(P) (Loss of 'FULL' Feedwater Heating)2(Reference 3)Core Thermal Power (%)EOOS CoreFlow (% 0.0 21.6 <33.3 >33.3 40.0 <60.0 >60.0 100.0Cmiainof Rated)III LHGRFAC(P) Base CaseDLO'< 500.628 1 0.628 I 0.682I 4 4-0.6440.990> 500.566 1 0.566 I 0.594I Two or MoreTBVOOSI i f"l %<-50 0.628 1 0.628 0.682 0.644* 50 0.566 1 0.566 0.594 1I -I-1 0.990 1-PROOS I 50 0.554 0.554 0.554 0.554 0.554 0.702 0.742 0.990DLO I > 50 0.554 0.554 0.554 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 58 Exelon Nuclear -Nuclear FuelsCLI C15 Core Operating Limits ReportNon-Proprietary Information Submitted inAccordance with 10 CFR 2.390DOC ID: COLR Clinton I Rev. 9Table 5-8Flow Dependent LHGR Multiplier LHGRFAC(F) for Base Case/PROOS (Loss of 'FULL' Feedwater Heating)' (Reference 3)Core Flow LHGRFAC(F) (% rated) ________F 0.0 0.43825.0 0.60630.0 0.64082.2 0.990109.0 0.990Table 5-9Flow Dependent LHGR Multiplier LHGRFAC(F) for Two or More TBVOOS(Loss of 'FULL' Feedwater Heating)1(Reference 3)Core Flow LHGRFAC(F) (% rated)0.0 0.13925.0 0.36130.0 0.40640.0 0.49550.0 0.62480.0 0.85198.3 0.990109.0 0.990'Linear interpolation should be used for points not listed in the table.Page 22 of 58 Exelon Nuclear -Nuclear FuelsCLIC15 Core Operating Limits ReportNon-Proprietary Information Submitted inAccordance with 10 CFR 2.390DOC ID: COLR Clinton I Rev. 96.0 Reactor Protection System (RPS) Instrumentation 6.1 Technical Specification

Reference:

Section 3.3.1.16.2

Description:

The Average Power Range Monitor (APRM) flow biased simulated thermal power-high time constant, shall be between 5.4 seconds and 6.6 seconds (Reference 6).7.0 Turbine Bypass System Parameters 7.1 Technical Specification

Reference:

Section 3.7.67.2

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 reactor thermalpower, minimum critical power ratio (MCPR), and linear heat generation rate (LHGR) limits must beused to comply with the assumptions in the design basis transient analysis. Table 7-1 provides the reactor thermal power limitations for an inoperable Main Turbine BypassSystem as specified in Technical Specification 3.7.6 action statement A.1. The MCPR and LHGRlimits for one TBVOOS are included in the Base Case for Cycle 15, as identified in Table 9-1. TheMCPR and LHGR limits for two or more TBVOOS are provided in Sections 4 and 5.Table 7-1Reactor Power Limitation -Turbine Bypass Valves Out of Service(References 2 and 3)Turbine Bypass System Status J Maximum Reactor Thermal Power (% Rated)One Turbine Bypass Valve 100.0Out of ServiceTwo or More Turbine Bypass Valves 97.0Out of Service 97.0Page 23 of 58 Exelon Nuclear -Nuclear FuelsCLIC15 Core Operating Limits ReportNon-Proprietary Information Submitted inAccordance with 10 CFR 2.390DOC ID: COLR Clinton I Rev. 98.0 Stability Protection Setpoints 8.1 Technical Specification

Reference:

Section 3.3.1.38.2

Description:

The Clinton 1 Cycle 15 OPRM Period Based Detection Algorithm (PBDA) Trip Setpoints for the OPRMSystem for use in Technical Specification 3.3.1.3 are found in Table 8-1 and 8-2. These values arebased on the cycle specific analysis documented in Reference 3.Any change to the OLMCPR value and/or ARTS-based power dependent MCPR limits should beevaluated for potential impact on the OPRM PBDA Trip Setpoints. Table 8-1OPRM PBDA Trip Setpoints (Valid for All Conditions) (Reference 3)P Corresponding Maximum Confirmation PBDA Trip Amplitude Count Trip Setting1.10 1 13Table 8-2OPRM PBDA Trip Setpoints -SLO1(Valid for SLO Conditions Only)(Reference 3)PBDATripAmpltud Corresponding Maximum Confirmation PBDATripAmpltudeCount Trip Setting1.15 16Notes for Table 8-2:1. The standard two loop operation OPRM Trip Setpoints specified in Table 8-1 must beimplemented prior to restarting the idle pump when exiting the SLO condition. Page 24 of 58 Exelon Nuclear -Nuclear FuelsCLIC15 Core Operating Limits ReportNon-Proprietary Information Submitted inAccordance with 10 CFR 2.390DOC ID: COLR Clinton 1 Rev. 99.0 Modes of Operation The Allowed Modes of Operation with combinations of Equipment Out-of-Service (EOOS) are asdescribed below in Table 9-1:Table 9-1Modes of Operation (Reference 3)_____________O _____p_ Operating RegionEOOS Options2 Standard MELLLA ICF ] FFWTR1 ] Coastdown Base Case DLO3 Yes Yes Yes Yes YesBase Case SLO1'3 Yes No No No YesPROOS DLO3 Yes Yes Yes Yes YesPROOS SLO1'3 Yes No No No YesTwo or More TBVOOS DLO4 Yes Yes Yes Yes YesTwo or More TBVOOS SLO' 4 Yes No No No YesNotes:1. Concurrent operation with SLO and Loss of'FULL' Feedwater Heating (+/-10 *F outside design NORMAL temperature, meaning changes in feedwater temperature greater than 10 'F and less than or equal to 50 'F) or FFWTR has not beenevaluated and thus is not a valid operating mode. (Reference 8)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 incycle operation in Dual Loop mode.4. Includes 2 SRVOOS, 1 ADSOOS, and up to a 50TF feedwater temperature reduction (FWTR includes feedwater heaterOOS or final feedwater temperature reduction) at any point in cycle operation in Dual Loop mode.Page 25 of 58 Exelon Nuclear -Nuclear Fuels DOC ID: COLR Clinton I Rev. 9CLIC15 Core Operating Limits ReportNon-Proprietary Information Submitted inAccordance with 10 CFR 2.39010.0 Methodology The analytical methods used to determine the core operating limits shall be those previously reviewed andapproved 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 US, May 2012 and U.S. Supplement NEDE-24011-P-A-19-US, May 2012.2. "BWR Owners' Group Reactor Stability Detect and Suppress Solutions Licensing Basis Methodology andReload Applications",

NEDO-32465, August 199611.0 References

1. Nuclear Regulatory Commission, Technical Specifications for Clinton Power Station Unit 1,Docket No. 50-461, License No. NPF-62.2. GE Hitachi Nuclear Energy Report, 0000-0086-4634-R2-P, "Clinton Power Station One Bypass Out of Serviceor Turbine Bypass System out of Service Analysis

-Final", July 2010.3. Global Nuclear Fuel Document, 0000-0154-8722-SRLR Revision 0, "Supplemental ReloadLicensing Report for Clinton Power Station Unit 1 Reload 14 Cycle 15", August 2013.4. Global Nuclear Fuel Document, 0000-0154-8722-FBIR-P Revision 0, "Fuel Bundle Information Report for Clinton Power Station Unit 1 Reload 14 Cycle 15", August 2013.5. General Electric

Document, GE-NE-0000-0000-7456-01 P, "Option B Scram Times For ClintonPower Station",

February 2002.6. Exelon Transmittal of Design Information, TODI ES1300006 Revision 0, "Resolved OPL-3Parameters for Clinton Cycle 15", May 9, 2013.7. GE Hitachi Nuclear Energy Letter, CFL-EXN-LH1-12-059, "Affirmation of the Clinton PowerStation Unit 1 MAPLHGR Reduction for Feedwater Riser Flow Asymmetry", April 25, 2012.8. General Electric

Document, GE-NE-0000-0026-1857-Ri, "Evaluation of Operation WithEquipment Out-Of-Service for the Clinton Power Station",

June 28, 2004.9. Exelon Technical Evaluation, EC 400895, Rev. 0, "Modified Off-rated Kps for Clinton PowerStation", February 2015.Page 26 of 58 Exelon Nuclear -Nuclear FuelsCLIC15 Core Operating Limits ReportNon-Proprietary Information Submitted inAccordance with 10 CFR 2.390DOC ID: COLR Clinton I Rev. 9Appendix APage 27 of 58 Exelon Nuclear -Nuclear FuelsCLIC15 Core Operating Uimits ReportNon-Proprietary Infornation Submitted inAccordance with 10 CFR 2.390G NF.Global Nuclear FuelDOC ID: COLR Clinton I Rev. 9Global Nuclear FuelIA Joint Venture of GE,Toshiba. & Hitachi0000-0154-8722-FBIR-NP Revision 0Class IAugust 2013Non-Proprietary Information -Class I (Public)Fuel Bundle Information ReportforClinton Power Station Unit 1Reload 14 Cycle 15Copyright 2013 Global Nuclear Fuel -Americas, LLCAll Rights ReservedPage 28 of 58 Exelon Nuclear -Nuclear FuelsCLIC15 Core Operating Uimits ReportNon-Proprietary Information Submitted inAccordance with 10 CFR 2.390DOC ID: COLR Clinton I Rev. 9IClintonReload 14Non-Proprietary Information -Class I (Public)0000-01 54-8722-FBIR-NP Revision 0Important Notice Regarding Contents of This ReportPlease 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 truerepresentation of the facts known by, obtained by or provided to GNF-A at the time this report wasprepared. The only undertakings of GNF-A respecting the Information are contained in the contract betweenRecipient and GNF-A for nuclear fuel and related services for the Nuclear Plant (the "Fuel Contract") andnothing contained in this document shall be construed as amending or modifying the Fuel Contract. Theuse 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 anyrepresentation or warranty (either expressed or implied) as to the completeness, accuracy or usefulness ofthe Information or that such unauthorized use may not infringe privately owned rights, nor (b) assumesany responsibility for liability or damage of any kind which may result from such use of suchinformation. Information NoticeThis is a non-proprietary version of the document 0000-0154-8722-FBIR-P, Revision 0, which has theproprietary information removed. Portions of the document that have been removed are indicated by anopen and closed bracket as shown here [[Page 2Page 29 of 58 Exelon Nuclear -Nuclear FuelsCLIC15 Core Operating Umits ReportNon-Proprietary Information Submitted inAccordance with 10 CFR 2.390DOC ID: COLR Clinton I Rev. 9IClintonR~Inocd 14Non-Proprietary Information -Class I (Public)0000-01 54-8722-FBIR-NP Revision 0Reload 141. Introduction and SummaryThis 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 PowerStation Unit I for Cycle 15. These LHGR limits are obtained from thermal-mechanical considerations only. Approved GNF-A calculation models documented in Reference I were used in performing thisanalysis. LHGR limits as a function of exposure for each bundle of the core design are given in Appendix A. TheLHGR 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 totwo places past the decimal.Appendix B contains a description of the fuel bundles. Table B-I contains a summary of bundle-specific information, and the figures provide the enrichment distribution and gadolinium distribution for the fuelbundles included in this appendix. These bundles have been approved for use under the fuel licensing acceptance criteria of Reference 1.Page 3Page 30 of 58 Exelon Nuclear -Nuclear FuelsCLIC15 Core Operating Umits ReportNon-Proprietary Information Submitted inAccordance with 10 CFR 2.390DOC ID: COLR Clinton I Rev. 9IClintonReload 14Non-Proprietary Information -Class I (Public)0000-01 54-8722-FBIR-NP Revision

02. References

1. General Electric Standard Application for Reactor Fuel, NEDE-2401 I-P-A- 19, May 2012; and theU.S. Supplement, NEDE-2401 1-P-A-19-US, May 2012.Page 4Page 31 of 58 Exelon Nuclear -Nuclear FuelsCLIC15 Core Operating ULmits ReportNon-Proprietary Informaflon Submitted inAccordance with 10 CFR 2.390DOC ID: COLR Clinton I Rev. 90000-0154-8722-FBIR-NP Revision 0IClintonD =1-. A 1 ANon-Proprietary Information

-Class I (Ptbiheic -Class I (Public) Revision 0Appendix AUO21Gd Thermal-Mechanical LHGR LimitsBundle Type: GEl 4-P 0OSNAB4I 8-15GZ-120T-150-T6-3240 (GE14C)Bundle Number: 3240Peak Pellet Exposure U02 LHGR LimitGWd/MT (GWd/ST) kW/ftErPeak Pellet Exposure Most Limiting Gadolinia LHGR Limit'GWd/MT (GWd/ST) kW/ft[rBounding gadolinia LHGR limit for all gadolinium Er ]].concentrations occurring in this bundle designPage 5Page 32 of 58 Exelon Nuclear -Nuclear FuelsCLI C15 Core Operating Limits ReportNon-Proprietary Information Submitted inAccordance with 10 CFR 2.390DOC ID: COLR Clinton I Rev. 9IClintonReload 14Non-Proprietary Information -Class I (Public)0000-01 54-8722-FBIR-NP Revision 0UO2/Gd Thermal-Mechanical LHGR LimitsBundle Type: GE 141-P IOSCOB405-13 GZ-120T-150-T6-3243 (GE 141)Bundle Number: 3243Peak Pellet Exposure U02 LHGR LimitGWd/MT (GWd/ST) kW/ft[[iPeak Pellet Exposure Most Limiting Gadolinia LHGR Limit 2GWd/MT (GWd/ST) kW/ft[[_____________________ 2 BoUnding gadolinia LHGR limit foi all gadolinium concettrations occurring in this bundle designPage 6Page 33 of 58 Exelon Nuclear -Nuclear FuelsCLIC15 Core Operating Uimits ReportNon-Proprietary Information Submitted inAccordance with 10 CFR 2.390DOC ID: COLR Clinton I Rev. 90000-0 1 54-8722-FBIR-NP Revision 0IClintonReload 14Non-Proprietary Information -Class I (Public)UO21Gd Thermal-Mechanical LHGR LimitsBundle Type: GEI4-PIOSNAB418-15GZ-120T-150-T6-3242 (GEI4C)Bundle Number: 3242Peak Pellet Exposure U02 LHGR LimitGWd/MT (GWd/ST) kW/ftPeak Pellet Exposure Most Limiting Gadolinia LHGR Limit 3GWd/MT (GWd/ST) kW/ft[[l_______________________________ ]]Bounding gadolinia LHGR limit for all gadolinium [[ ]]concentrations occurring in this bundle designPage 7Page 34 of 58 Exelon Nuclear -Nuclear FuelsCLIC15 Core Operating Limits ReportNon-Proprietary linformation Submitted inAccordance with 10 CFR 2.390Clinton Non-Proprietary Infonnation Reload 14 -Class I (Public)DOC ID: COLR Clinton I Rev. 90000-01 54-8722-FBIR-NP Revision 0IUQ2IGd Thermal-Mechanical LHGR LimitsBundle Type: GE 14-P I OSNAB422-13GZ-120T- 150-T6-3239 (GE 14C)Bundle Number: 3239Peak Pellet Exposure U02 LHGR LimitGWd/MT (GWd/ST) kW/ftPeak Pellet Exposure Most Limiting Gadolinia LHGR Limit 4GWd/MT (GWd/ST) kW/ft[[I___________________ 4 Bounding gadolinia L1-GR limit for all gadolinium concentrations occurring in this bundle designPage 8Page 35 of 58 Exelon Nuclear -Nuclear FuelsCLIC15 Core Operating Uimits ReportNon-Proprietary Information Submitted inAccordance with 10 CFR 2.390DOC ID: COLR Clinton I Rev. 90000-01 54-8722-FBIR-NP Revision 0IClintonReload 14Non-Proprietary Information -Class I (Public)UO21Gd Thermal-Mechanical LHGR LimitsBundle Type: GEl 4-P I OSNAB418-15GZ-1 20T- 150-T6-3241 (GE I 4C)Bundle Number: 3241Peak Pellet Exposure U02 LHGR LimitGWd/MT (GWd/ST) kW/ftErPeak Pellet Exposure Most Limiting Gadolinia LHGR Limit'GWd/MT (GWd/ST) kW/ftEr5 Bounding gadolinia LHGR limit for all gadolinium concentrations occurring in this bundle design[[ I].Page 9Page 36 of 58 Exelon Nuclear-Nuclear FuelsCLIC15 Core Operating Limits ReportNon-Proprietary Information Submitted inAccordance with 10 CFR 2.390DOC ID: COLR Clinton I Rev. 90000-0 1 54-8722-FBIR-NP Revision 0IClintonReload 14Non-Proprietary Information -Class I (Puhlic') UQ2IGd Thermal-Mechanical LHGR LimitsBundle Type: GNF2-PI 0SG2B402-15GZ-120T2-150-T6-4009 (GNF2)Bundle Number: 4009Peak Pellet Exposure UOz LHGR LimitGWd/MT (GWd/ST) kW/ft[[Peak Pellet Exposure Most Limiting Gadolinia LHGR Limit 6GWd/MT (GWd/ST) kW/ft[[_______________________________ ]],Bounding gadolinia LHGR limit for all gadolinium concentrations occurring in this bundle designPage 10Page 37 of 58 Exelon Nuclear -Nuclear FuelsCLIC15 Core Operating Umits ReportNon-Proprietary Information Submitted inAccordance with 10 CFR 2.390DOC ID: COLR Clinton I Rev. 9 1ClintonReload 14Non-Proprietary Information -Class I (PIiblic) 0000-01 54-8722-FBIR-NP Revision 0UO21Gd Thermal-Mechanical LHGR LimitsBundle Type: GNF2-P 10SG2B401-15GZ-120T2-150-T6-4010 (GNF2)Bundle Number: 4010Peak Pellet Exposure U02 LHGR LimitGWd/MT (GWd/ST) kW/ft[[IPeak Pellet Exposure Most Limiting Gadolinia LHGR Limit7GWd/MT (GWd/ST) kW/ftR[Bounding gadolinia LHGR limit for all gadolinium i .concentrations occurring in this bundle designPage 11Page 38 of 58 Exelon Nuclear -Nuclear FuelsCLIC15 Core Operating Umits ReportNon-Proprietary Information Submitted inAccordance with 10 CFR 2.390DOC ID: COLR Clinton I Rev. 90000-0 1 54-8722-FBIR-NP Revision (1IClintonRolný r 1ANon-Proprietary Information -Class I (Puthlic-Class I (Public) Revision 0UO2lGd Thermal-Mechanical LHGR LimitsBundle Type: GNF2-P 1OSG2B402-12G7.0-120T2-150-T6-401 I (GNF2)Bundle Number: 4011Peak Pellet Exposure U02 LHGR LimitGWd/MT (GWd/ST) kW/ftPeak Pellet Exposure Most Limiting Gadolinia LHGR Limit8GWd/MT (GWd/ST) kW/ftEr________________________________I Bounding gadolnia LHGR liiiii for all gadolinium concentrations occunring in this bundle designPage 12Page 39 of 58 Exelon Nuclear -Nuclear FuelsCLIC15 Core Operating Umits ReportNon-Proprietary Information Submitted inAccordance with 10 CFR 2.390Clinton Non-Proprietary Information Reload 14 -Class I (Public)DOC ID: COLR Clinton I Rev. 90000-01 54-8722-FBIR-NP Revision 0IUO21Gd Thermal-Mechanical LHGR LimitsBundle Type: GNF2-P I 0SG2B402-14GZ-1 20T2-150-T6-4012 (GNF2)Bundle Number: 4012Peak Pellet Exposure U02 LHGR LimitGWd/MT (GWd/ST) kW/ftI[[Peak Pellet Exposure Most Limiting Gadolinia LHGR Limit9GWd/MT (GWd/ST) kW/ft[II9 Bounding gadolinia LHGR limit lbr all gadolinium concentrations occurring in this bundle designPage 13Page 40 of 58 Exelon Nuclear-Nuclear FuelsCLIC15 Core Operating Umits ReportNon-Proprietary Information Submitted inAccordance with 10 CFR 2.390DOC ID: COLR Clinton I Rev. 90000-01 54-8722-FBIR-NP Revision 0IClintonReload 14Non-Proprietary Infornation -Class I (Public)UO2/Gd Thermal-Mechanical LHGR LimitsBundle Type: GNF2-PI 0SG2B383-14GZ-120T2-150-T6-4252 (GNF2)Bundle Number: 4252Peak Pellet Exposure UO2 LHGR LimitGWd/MT (GWd/ST) kW/ft[[Peak Pellet Exposure Most Limiting Gadolinia LHGR Limit'0GWd/MT (GWd/ST) kW/ft[[_______________________________ ]]"0 Bounding gadolinia LHGR limit lor all gadolinium concentrations occurring in this bundle designEr R].Page 14Page 41 of 58 Exelon Nuclear -Nuclear FuelsCLIC15 Core Operating Umits ReportNon-Proprietary Information Submitted inAccordance with 10 CFR 2.390DOC ID: COLR Clinton I Rev. 90000-01 54-8722-FBIR-NP Revision 0IClintonReload 14Non-Proprietary Information -Class I (Public)UO21Gd Thermal-Mechanical LHGR LimitsBundle Type: GNF2-P I 0SG2B384-l4GZ-120T2-150-T6-4253 (GNF2)Bundle Number: 4253Peak Pellet Exposure U02 LHGR LimitGWd/MT (GWd/ST) kW/ftE[Peak Pellet Exposure Most Limiting Gadolinia LHGR Limit'1GWd/MT (GWd/ST) kW/ftEr_____________________________ ]]Bounding gadolinia L1-GR limit lbr all gadolinium concentrations occurring in this bundle designPage 15Page 42 of 58 Exelon Nuclear -Nuclear FuelsCLIC15 Core Operating Limits ReportNon-Proprietary Information Submitted inAccordance with 10 CFR 2.390DOC ID: COLR Clinton I Rev. 90000-01 54-8722-FBIR-NP Revision 0IClintonReload 14Non-Proprietary Information -Class I (Piuhlip.c Reload 14U02/Gd Thermal-Mechanical LHGR LimitsBundle Type: GNF2-P I 0SG2B383-14GZ-120T2-150-T6-4254 (GNF2)Bundle Number: 4254Peak Pellet Exposure U02 LHGR LimitGWd/MT (GWd/ST) kW/ftPeak Pellet Exposure Most Limiting Gadolinia LHGR Limit'2GWd/MT (GWd/ST) kW/ftEr12 Bounding gadoiinia LHGR limit for ail gadolinium concentrations occurring in this bundle designPage 16Page 43 of 58 Exelon Nuclear -Nuclear FuelsCLIC15 Core Operating Umits ReportNon-Proprietary Information Submitted inAccordance with 10 CFR 2.390DOC ID: COLR Clinton I Rev. 9 1ClintonReload 14Non-Proprietary Information -Class T (Puhlic)0000-01 54-8722-FBIR-NP Revision 0UO21Gd Thermal-Mechanical LHGR LimitsBundle Type: GNF2-P I 0SG2B396-12G5.0-120T2-150-T6-4255 (GNF2)Bundle Number: 4255Peak Pellet Exposure U02 LHGR LimitGWd/MT (GWd/ST) kW/ftPeak Pellet Exposure Most Limiting Gadolinia LHGR Limit ,3GWd/MT (GWd/ST) kW/ftEr'3 Bounding gadolinia LHGR limit for all gadolinium [[ ]1.concentrations occurring in this bundle designPage 17Page 44 of 58 Exelon Nuclear -Nuclear FuelsCLIC15 Core Operating Limits ReportNon-Proprietary Information Submitted inAccordance with 10 CFR 2.390DOC ID: COLR Clinton I Rev. 9IClintonReload 14Non-Proprietary Information -Class I (Piihlic) 0000-01 54-8722-FBIR-NP Revision 0Appendix BFuel Bundle Information Table B-IBundle Specific Information Fuel Bundle Enrichment Weight Weight Max Exposureof UO2 ofU k- at at Max kTBundle Number (wt% U-235) 200C GWd/MT(kg) (kg) i~ (GWd/ST)GE14-P 1OSNAB418-15GZ-120T- 150-T6-3240 (GE 14C)GEI41-PIOSCOB405-13GZ-3243120T-150-T6-3243 (GEl41)GEI4-P10SNAB418-15GZ-120T- 150-T6-3242 (GE I4C)GE I4-PIOSNAB422-13GZ-120T-150-T6-3239 (GE14C)GE 14-PIOSNAB418-15GZ-3241120T-150-T6-3241 (GE14C)GNF2-P I 0SG2B402-15GZ-120T2-150-T6-4009 (GNF2)GNF2-P I OSG2B401-15GZ-120T2-150-T6-4010 (GNF2)GNF2-P 10SG2B402-12G7.0-4011120T2-150-T6-4011 (GNF2)GNF2-P 10SG2B402-14GZ-120T2-150-T6-4012 (GNF2)GNF2-P l 0SG2B3383-14GZ-120T2-150-T6-4252 (GNF2)GNF2-P I 0SG2B384-14GZ-120T2-150-T6-4253 (GNF2)GNF2-P10SG2B383-14GZ-120T2-150-T6-4254 (GNF2)GNF2-P10SG2B396-12G5.0-4255120T2-150-T6-4255 (GNF2)14 Maximum lattice k. for the most reactive uncontrolled state plus a [[]] adder for uncertainties. Page 18Page 45 of 58 Exelon Nuclear -Nuclear FuelsCLIC15 Core Operating ULmits ReportNon-Proprietary Information Submitted inAccordance with 10 CFR 2.390DOC ID: COLR Clinton I Rev. 9IClintonReload 14Non-Proprietary Information -Class I (Public)0000-01 54-8722-FBIR-NP Revision 011lFigure B-1 Enrichment and Gadolinium Distribution for EDB No. 3240Fuel Bundle GEI4-PIOSNAB418-15GZ-120T-150-T6-3240 (GEI4C)Page 19Page 46 of 58 Exelon Nuclear -Nuclear FuelsCLIC15 Core Operating ULmits ReportNon-Proprietary infrmation Submitted inAccordance with 10 CFR 2.390DOC ID: COLR Clinton I Rev. 9IClintonReload 14Non-Proprietary Information -Class I (Public)0000-01 54-8722-FBIR-NP Revision 0Figure B-2 Enrichment and Gadolinium Distribution for EDB No. 3243Fuel Bundle GEl41-PIOSCOB405-13GZ-120T-I50-T6-3243 (GEl41)Page 20Page 47 of 58 Exelon Nuclear -Nuclear FuelsCLIC15 Core Operating Umits ReportNon-Proprietary Infornation Submitted inAccordance with 10 CFR 2.390DOC ID: COLR Clinton I Rev. 9IClintonReload 14Non-Proprietary Information -Class I (Public)0000-01 54-8722-FBIR-NP Revision 0[[1]Figure B-3 Enrichment and Gadolinium Distribution for EDB No. 3242Fuel Bundle GE14-P1OSNAB418-15GZ-120T-150-T6-3242 (GE14C)Page 21Page 48 of 58 Exelon Nuclear -Nuclear FuelsCLIC15 Core Operating Umits ReportNon-Proprietary Information Submitted inAccordance with 10 CFR 2.390DOC ID: COLR Clinton I Rev. 9IClintonReload 14Non-Proprietary Information -Class I (Public)0000-01 54-8722-FBIR-NP Revision 0[[Figure B-4 Enrichment and Gadolinium Distribution for EDB No. 3239Fuel Bundle GEl 4-PI OSNAB422-13GZ-1 20T-150-T6-3239 (GEl 4C)Page 22Page 49 of 58 Exelon Nuclear -Nuclear FuelsCLIC15 Core Operating Umits ReportNon-Proprietary Information Submitted inAccordance with 10 CFR 2.390DOC ID: COLR Clinton I Rev. 9IClintonReload 14Non-Proprietary Information -Class I (Public)0000-0154-8722-FBIR-NP Revision 0[[Figure B-5 Enrichment and Gadolinium Distribution for EDB No. 3241Fuel Bundle GEl 4-Pt OSNAB418-15GZ-1 20T-1 50-T6-3241 (GE14C)Page 23Page 50 of 58 Exelon Nuclear -Nuclear FuelsCLIC15 Core Operating Umits ReportNon-Proprietary Information Submitted inAccordance with 10 CFR 2.390DOC ID: COLR Clinton I Rev. 9IClintonReload 14Non-Proprietary Information -Class I (Public)0000-01 54-8722-FBIR-NP Revision 0[[Figure B-6 Enrichment and Gadolinium Distribution for EDB No. 4009Fuel Bundle GNF2-P1OSG2B402-15GZ-120T2-150-T6-4009 (GNF2)Page 24Page 51 of 58 Exelon Nuclear -Nuclear FuelsCLIC15 Core Operating Umits ReportNon-Proprietary Informnation Submitted inAccordance with 10 CFR 2.-g0DOC ID: COLR Clinton I Rev. 9IClintonReload 14Non-Proprietary Information -Class I (Public)0000-01 54-8722-FBIR-NP Revision 0[[Figure B-7 Enrichment and Gadolinium Distribution for EDB No. 4010Fuel Bundle GNF2-P1OSG2B401-15GZ-120T2-150-T6-4010 (GNF2)Page 25Page 52 of 58 Exelon Nuclear -Nuclear FuelsCLIC15 Core Operating Umits ReportNon-Proprietary Information Submitted inAccordance with 10 CFR 2.390DOC ID: COLR Clinton I Rev. 9IClintonR 14Non-Proprietary Information -Class I (Public)0000-01 54-8722-FBIR-NP Revision 0Reload 14Figure B-8 Enrichment and Gadolinium Distribution for EDB No. 4011Fuel Bundle GNF2-PIOSG2B402-12G7.0-120T2-150-T6-4011 (GNF2)Page 26Page 53 of 58 Exelon Nuclear -Nuclear FuelsCLIC15 Core Operating Uimits ReportNon-Proprietary Information Submitted inAccordance with 10 CFR 2.390DOC ID: COLR Clinton I Rev. 9IClintonReload 14Non-Proprietary Information -Class I (Public)0000-0154-8722-FBIR-NP Revision 011l]]Figure B-9 Enrichment and Gadolinium Distribution for EDB No. 4012Fuel Bundle GNF2-PIOSG2B402-14GZ-120T2-150-T6-4012 (GNF2)Page 27Page 54 of 58 Exelon Nuclear-Nuclear FuelsCLIC15 Core Operating Umits ReportNon-Proprietary Information Submitted inAccordance with 10 CFR 2.390DOC ID: COLR Clinton I Rev. 9IClintonReload 14Non-Proprietary Information -Class I (Public)0000-0154-8722-FBIR-NP Revision 0[[Figure B-10 Enrichment and Gadolinium Distribution for EDB No. 4252Fuel Bundle GNF2-PIOSG2B383-14GZ-120T2-150-T6-4252 (GNF2)Page 28Page 55 of 58 Exelon Nuclear -Nuclear FuelsCLIC15 Core Operating Umits ReportNon-Proprietary Information Submitted inAccordance with 10 CFR 2.390DOC ID: COLR Clinton I Rev. 9IClintonReload 14Non-Proprietary Information -Class I (Pubhlic') 0000-01 54-8722-FBIR-NP Revision 0IReload 14 -Class I (PUblic) Revision 0[IiFigure B-1 I Enrichment and Gadolinium Distribution for EDB No. 4253Fuel Bundle GNF2-PIOSG2B384-14GZ-120T2-150-T6-4253 (GNF2)Page 29Page 56 of 58 Exelon Nuclear -Nuclear FuelsCLIC15 Core Operating Umits ReportNon-Proprietary Information Submitted inAccordaice with 10 CFR 2.390DOC ID: COLR Clinton I Rev. 9IClintonRPl1-,A I1ANon-Proprietary Information -Class I (Public)0000-01 54-8722-FBIR-NP Revision 0[[Figure B-12 Enrichment and Gadolinium Distribution for EDB No. 4254Fuel Bundle GNF2-PIOSG2B383-14GZ-120T2-150-T6-4254 (GNF2)Page 30Page 57 of 58 Exelon Nuclear -Nuclear FuelsCLIC15 Core Operating Umits ReportNon-Proprietary Information Submitted inAccordance with 10 CFR 2.390DOC ID: COLR Clinton I Rev. 9IClintonReload 14Non-Proprietary Information -Class I (Puhlic)0000-01 54-8722-FBIR-NP Revision 0[[l1]Figure B-13 Enrichment and Gadolinium Distribution for EDB No. 4255Fuel Bundle GNF2-PIOSG2B396-12G5.0-120T2-150-T6-4255 (GNF2)Page 31Page 58 of 58}}