U-604201, Core Operating Limits Report Cycle 15, Revision 9

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Core Operating Limits Report Cycle 15, Revision 9
ML15069A045
Person / Time
Site: Clinton Constellation icon.png
Issue date: 02/27/2015
From:
Exelon Generation Co
To:
Office of Nuclear Reactor Regulation
References
U-604201
Download: ML15069A045 (62)
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Text

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 2 Core 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 - Americas AFFIDAVIT 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 to apply for its withholding.

(2) The information sought to be withheld is contained in GNF-A proprietary report 0000-01 54-8722-FBIR-P, Fuel Bundle Information Report for Clinton Power Station Unit 1 Reload 14 Cycle 15, Revision 0, August 2013. GNF-A proprietary information in 0000-01 54-8722-FBIR-P, Fuel Bundle Infornmation Reportfor Clinton Power Station Unit 1 Reload 14 Cycle 15, Revision 0, August 2013 is identified by a dotted underline inside double square brackets. ((This ".se..entence --. an..exampl.e... 3 )) Figures and large equation is --.

objects 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 basis for the proprietary determination.

(3) In making this application for withholding of proprietary information of which it is the owner or licensee, GNF-A relies upon the exemption from disclosure set forth in the Freedom 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 "trade secrets" (Exemption 4). The material for which exemption from disclosure is here sought also qualify under the narrower definition of "trade secret", within the meanings assigned to those terms for purposes of FOIA Exemption 4 in, respectively, Critical Mass Energy Project v. Nuclear Regulatory Commission, 975 F2d 871 (DC Cir. 1992), and Public Citizen 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 data and analyses, where prevention of its use by GNF-A's competitors without license from 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 to obtain 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 set forth 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 my knowledge 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 parties including any required transmittals to NRC, have been made, or must be made, pursuant to regulatory provisions or proprietary agreements which provide for maintenance of the information in confidence. Its initial designation as proprietary information, and the subsequent 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 the originating component, the person most likely to be acquainted with the value and sensitivity of the information in relation to industry knowledge, or subject to the terms under which it was licensed to GNF-A. Access to such documents within GNF-A is limited on a "need to know" basis.

(7) The procedure for approval of external release of such a document typically requires review by the staff manager, project manager, principal scientist or other equivalent authority, by the manager of the cognizant marketing function (or his delegate), and by the Legal Operation, for technical content, competitive effect, and determination of the accuracy of the proprietary designation. Disclosures outside GNF-A are limited to regulatory bodies, customers, and potential customers, and their agents, suppliers, and licensees, and others with 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 contains details of GNF-A's fuel design and licensing methodology. The development of this methodology, along with the testing, development and approval was achieved at a significant 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 database that 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 and technology base, and its commercial value extends beyond the original development cost.

The value of the technology base goes beyond the extensive physical database and analytical methodology and includes development of the expertise to determine and apply the appropriate evaluation process. In addition, the technology base includes the value derived 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 a substantial investment of time and money by GNF-A.

The precise value of the expertise to devise an evaluation process and apply the correct analytical 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 of the GNF-A experience to normalize or verify their own process or if they are able to claim an equivalent understanding by demonstrating that they can arrive at the same or similar conclusions.

The value of this information to GNF-A would be lost if the information were disclosed to the public. Making such information available to competitors without their having been required 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 are true and correct to the best of my knowledge, information, and belief.

Executed on this 27th day of August 2013.

Lukas Trosman Engineering Manager, Reload Design and Analysis Global.Nuclear Fuel - Americas, LLC 0000-01 54-8722-FBIR-P Affidavit Page 3 of 3

Exelon Nuclear- Nutclear Fuels DOC M: COLR Clinton i Rev. 9 CLICIS Core Operating Lmits Report Non-PmrupdUy InknmaUan Submfbd in Arrdance Wth IOCFR 2.300 CORE OPERATING LIMITS REPORT:

FOR CLINTON POWER STATION UNIT I CYCLE IS:

Prepared By.:

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Reviewed B. Date. 9i Reviewed By: m Date: z/a /,-,

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Reviewed By: D Date:____

independent Reviewer- FrPk W. Trikur Approved i

-9F c.ir7; Manager- James J. Tusar Date: 21 Station QL Reviewer By* Date:

Page I of 58

Exelon Nuclear - Nuclear Fuels DOC ID: COLR Clinton 1 Rev. 9 CLIC15 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 Parameters 23 8.0 Stability Protection Setpoints 24 9.0 Modes of Operation 25 10.0 Methodology 26 11.0 References 26 Appendix A 27 Page 2 of 58

Exelon Nuclear - Nuclear Fuels DOC ID: COLR Clinton I Rev. 9 CLIC15 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 3-4 MAPLHGR Multiplier for Loss of'FULL' Feedwater Heating 9 Table 4-1 Operating Limit Minimum Critical Power Ratio 12 Table 4-2 Power Dependent MCPR Limits MCPR(P) and Multipliers K(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 Two or More TBVOOS Table 4-7 Single Loop Operation (SLO) Flow Dependent MCPR Limits MCPR(F) 16 for Two or More TBVOOS Table 5-1 Linear Heat Generation Rate Limits for 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 Two or More TBVOOS 20 Table 5-6 LHGR Single Loop Operation (SLO) Reduction Factor 20 Page 3 of 58

Exelon Nuclear - Nuclear Fuels DOC ID: COLR Clinton 1 Rev. 9 CLI C15 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 Two or More TBVOOS 22 (Loss of 'FULL' Feedwater Heating)

Table 7-1 Reactor Power Limitation - Turbine Bypass Valves Out of Service 23 Table 8-1 OPRM PBDA Trip Setpoints 24 Table 8-2 OPRM PBDA Trip Setpoints - SLO 24 Table 9-1 Modes of Operation 25 Page 4 of 58

Exelon Nuclear - Nuclear Fuels DOC ID: COLR Clinton 1 Rev. 9 CLIC15 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 OOS, 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 (FWTR 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 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 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 58

Exelon Nuclear - Nuclear Fuels DOC ID: COLR Clinton 1 Rev. 9 CLLC15 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(s) Out of Service - valves are not credited for fast opening or for normal pressure control TCV Turbine Control Valve TSV Turbine Stop Valve Page 6 of 58

Exelon Nuclear - Nuclear Fuels DOC ID: COLR Clinton I Rev. 9 CLIC15 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 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

Page 7 of 58

Exelon Nuclear - Nuclear Fuels DOC ID: COLR Clinton 1 Rev. 9 CLLC15 Core Operating Limits Report Non-Proprietary Information Submitted in Accordance with 10 CFR 2.390 3.0 MAPLHGR Limits 3.0 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 heat generation rate (MAPLHGR) limit for GNF2 fuel. Limits listed in Table 3-1 and Table 3-2 are for dual reactor recirculation loop operation (DLO).

For single reactor recirculation loop operation (SLO), the MAPLHGR limits given in Table 3-1 and Table 3-2 must be multiplied by a SLO MAPLHGR multiplier provided in Table 3-3. The SLO MAPLHGR multiplier for all fuel types is 0.76 (Reference 3).

For Loss of 'FULL' Feedwater Heating (+/-10 'F outside design NORMAL temperature, meaning changes in feedwater temperature greater than 10 0F and less than or equal to 50 TF), the MAPLHGR limits given 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 3-1 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 1 (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 Linear interpolation should be used for points not listed in the table.

Page 8 of 58

Exelon Nuclear - Nuclear Fuels DOC ID: COLR Clinton I Rev. 9 CLI C15 Core Operating Limits Report Non-Proprietary Information Submitted in Accordance with 10 CFR 2.390 Table 3-3 MAPLHGR Single Loop Operation (SLO) Multiplier (Reference 3)

Fuel MAPLHGR Type SLO Multiplier All Fuel Types 0.760 Table 3-4 MAPLHGR Multiplier for Loss of 'FULL' Feedwater Heating (Reference 7)

Fuel MAPLHGR Type Multiplier All Fuel Types 0.990 Page 9 of 58

Exelon Nuclear - Nuclear Fuels DOC ID: COLR Clinton I Rev. 9 CLIC15 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.

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 58

Exelon Nuclear - Nuclear Fuels DOC ID: COLR Clinton I Rev. 9 CLIC15 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 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 average insertion time of 0.516 seconds (Reference 6).

To utilize the MCPR limits for the Option B scram speed, the cycle average scram insertion time for 20% insertion must satisfy equation 2 in Reference 5 Section 4. If the cycle average scram insertion time does not meet the Option B criteria, the appropriate MCPR value may be determined from a linear interpolation between the Option A and B limits as specified by equation 4 in Reference 5 Section 4.

4.1.4 Recirculation Flow Control Valve Settings Cycle 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 all runout events (Reference 3).

Page II of 58

Exelon Nuclear - Nuclear Fuels DOC ID: COLR Clinton I Rev. 9 CLIC15 Core Operating Limits Report Non-Proprietary Information Submitted in Accordance with 10 CFR 2.390 Table 4-1 Operating Limit Minimum Critical Power Ratio (Reference 3)

GE14C2 and GNF2 GE14C2 and GNF2 EOOS Fuel Option A Fuel Option B Combination All Exposures All Exposures Base Case 1.431 1.431 DLO 4 1.431 1.431 Base Case SL0 3.

4 1.43 1.43 PROOS DPOS4 1.431 1.431 PROOS SLO3,4 1.43 1.43 Two or More 1 TBVOOS DLO Two or More TBVOOS SLO 3 1.46 1.43 Notes 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 OLMCPR value, whichever is highest.
4. Includes TCV and/or TSV stuck closed, 1 TBVOOS.

Page 12 of 58

Exelon Nuclear - Nuclear Fuels DOC ID: COLR Clinton I Rev. 9 CLI C15 Core Operating Limits Report Non-Proprietary Information Submitted in Accordance with 10 CFR 2.390 Table 4-2 12 Power Dependent MCPR Limits MCPR(P) and Multipliers K(P) '

(References 3 and 9)

EQOS Core Flow Core Thermal Power (%)

7 0 .0 100.0 E C(% of Rated) 121.6 1<33.3 0.0 MCPR(P) >33.3 <70.0 1P>

K(P)

Base Case 4 DLO  :< 50 2.31 2.31 2.10 GNF2/GE14C 3 1.351 1.212 1.163 1.000 Option A > 50 2.46 2.46 2.17 Base Case 4 DLO <50 2.31 2.31 2.10 GNF2/GE14C 1.228 1.102 1.057 1.000 Option B5 > 50 2.46 2.46 2.17 Base Case 4 DLO <50 2.38 2.38 2.17 GE141 1.234 1.107 1.062 1.000 Option B5 > 50 2.53 2.53 2.24 Base Case4 SLO <50 2.34 2.34 2.13 GNF2/GE14C 3 1.351 1.212 1.163 1.000 Option A/B > 50 2.49 2.49 2.20 Two or More <50 2.31 2.31 2.10 TBVOOS DLO GNF2/GE14C3 1.351 1.212 1.163 1.000 Option A/B > 50 2.46 2.46 2.17 Two or More < 50 2.34 2.34 2.13 TBVOOS SLO 1 1.351 1.212 1.163 1.000 GNF2/GE14C3 Option A/B > 50 2.49 2.49 2.20 Notes 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 with Option B Scram Times.

Page 13 of 58

Exelon Nuclear - Nuclear Fuels DOC ID: COLR Clinton 1 Rev. 9 CLI C15 Core Operating Limits Report Non-Proprietary Information Submitted in Accordance with 10 CFR 2.390 Table 4-3 12 PROOS Power Dependent MCPR Limits MCPR(P) and Multipliers K(P) '

(References 3 and 9)

Core Core Thermal Power (%)

EQOS Combination -(% 33.3 60.0 <85.0 >85.0 of Rated) MCPR(P) K(P)

PROOS 4 DLO < 50 2.31 2.31 2.10 GNF2/GE14C 3 1.558 1.436 1.309 1.084 1.000 Option A > 50 2.46 2.46 2.17 PROOS 4 DLO < 50 2.31 2.31 2.10 GNF2/GE14C 1.416 1.305 1.190 1.0296 1.000 Option B5 > 50 2.46 2.46 2.17 PROOS 4 DLO < 50 2.38 2.38 2.17 GE141 1.423 1.312 1.196 1.0316 1.000 Option B > 50 2.53 2.53 2.24 PROOS 4 SLO <50 2.34 2.34 2.13 GNF2/GE14C 3 1.558 1.436 1.309 1.084 1.000 Option A/B > 50 2.49 2.49 2.20 Notes 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 with Option B Scram Times.
6. Base Case K(P) is bounding and was interpolated for PROOS.

Page 14 of 58

Exelon Nuclear - Nuclear Fuels DOC ID: COLR Clinton 1 Rev. 9 CLI C15 Core Operating Limits Report Non-Proprietary Information Submitted in Accordance with 10 CFR 2.390 Table 4-4 Dual Loop Operation (DLO) Flow Dependent MCPR Limits MCPR(F) for Base Case/PROOS' (Reference 3)

Core Flow MCPR(F) MCPR(F)

(% rated) GNF2/GE14C GE141 0.0 1.88 1.95 25.0 1.70 1.77 84.1 1.27 _

93.7 - 1.27 109.0 1.27 1.27 Table 4-5 Single Loop Operation (SLO) Flow Dependent MCPR Limits MCPR(F) for Base Case/PROOS1 (Reference 3)

Core Flow MCPR(F) MCPR(F)

(% rated) GNF2/GE14C GE141 0.0 1.91 1.98 25.0 1.73 1.80 84.1 1.30 _

93.7 - 1.30 109.0 1.30 1.30 Linear interpolation should be used for points not listed in the table.

Page 15 of 58

Exelon Nuclear - Nuclear Fuels DOC ID: COLR Clinton 1 Rev. 9 CLIC15 Core Operating Limits Report Non-Proprietary Information Submitted in Accordance with 10 CFR 2.390 Table 4-6 Dual Loop Operation (DLO) Flow Dependent MCPR Limits MCPR(F) for Two or More TBVOOS 1 (Reference 3)

Core Flow MCPR(F) MCPR(F)

(% rated) GNF2/GE14C GE141 0.0 2.04 2.11 25.0 1.85 1.92 100.0 1.27 _

109.0 1.27 1.27 Table 4-7 Single Loop Operation (SLO) Flow Dependent MCPR Limits MCPR(F) for Two or More TBVOOS 1 (Reference 3)

Core Flow MCPR(F) MCPR(F)

(% rated) GNF2/GE14C GE141 0.0 2.07 2.14 25.0 1.88 1.95 100.0 1.30 j 109.0 1.30 1.30 Linear 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. 9 CLIC15 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 OF outside design NORMAL temperature, meaning changes 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 been evaluated and thus is not a valid operating mode. (Reference 8)

Page 17 of 58

Exelon Nuclear - Nuclear Fuels DOC ID: COLR Clinton 1 Rev. 9 CLI C15 Core Operating Limits Report Non-Proprietary Information Submitted in Accordance with 10 CFR 2.390 Table 5-1 Linear Heat Generation Rate Limits for U0 2 Rods 1 (Reference 4)

Fuel Type LHGR Limit GNF2 See Appendix A GE14C See Appendix A GE141 See Appendix A Table 5-2 Linear Heat Generation Rate Limits for Gad Rods1 (Reference 4)

Fuel Type LHGR Limit GNF2 See Appendix A GE14C See Appendix A GE141 See Appendix A Linear 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. 9 CLIC15 Core Operating Limits Report Non-Proprietary Information Submitted in Accordance with 10 CFR 2.390 Table 5-3 2 Power Dependent LHGR Multiplier LHGRFAC(P)

(Reference 3)

Core Thermal Power (%)

Core EOOS Co on Flow Flof 0.0 21.6 <33.3 >33.3 40.0 <60.0 >60.0 Combination (% of 100.0 Rated) _ _ __ L_

LHGRFAC(P)

Base Case1 < 50 0.634 0.634 0.689 0.651 - - - 1.000 DLO/SLO > 50 0.572 0.572 0.600 Two or More < 50 0.634 0.634 0.689 TBVOOS 0.651 - - - 1.000 DLO/SLO > 50 0.572 0.572 0.600 PROOS 1 < 50 0.560 0.560 0.560 DLO/SLO > 50 0.560 0.560 0.560 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 58

Exelon Nuclear - Nuclear Fuels DOC ID: COLR Clinton 1 Rev. 9 CLI C15 Core Operating Limits Report Non-Proprietary Information Submitted in Accordance with 10 CFR 2.390 Table 5-4 Flow Dependent LHGR Multiplier LHGRFAC(F) for Base Case/PROOS1 (Reference 3)

Core Flow LHGRFA

(% rated) 0.0 0.442 25.0 0.612 30.0 0.646 82.2 1.000 109.0 1.000 Table 5-5 Flow Dependent LHGR Multiplier LHGRFAC(F) for Two or More TBVOOS 1 (Reference 3)

Core Flow LHGRFAC(F)

(% rated) 0.0 0.140 25.0 0.365 30.0 0.410 40.0 0.500 50.0 0.630 80.0 0.860 98.3 1.000 109.0 1.000 Table 5-6 LHGR Single Loop Operation (SLO) Reduction Factor (Reference 3)

FuelSL LHGR TypeType SLO Multiplier All Fuel Types 0.760 1 Linear interpolation should be used for points not listed in the table.

Page 20 of 58

Exelon Nuclear - Nuclear Fuels DOC ID: COLR Clinton I Rev. 9 CLIC15 Core Operating Limits Report Non-Proprietary Information Submitted In Accordance with 10 CFR 2.390 Table 5-7 Power Dependent LHGR Multiplier LHGRFAC(P) 2 (Loss of 'FULL' Feedwater Heating)

(Reference 3)

Core Thermal Power (%)

EOOS Core Cmiainof Flow (% 0.0 21.6 <33.3 >33.3 40.0 <60.0 >60.0 100.0 Rated)III LHGRFAC(P)

Base Case < 50 0.628 4 1 0.628 I 4-0.682 I 0.644 0.990 DLO' > 50 0.566 1 0.566 I 0.594 I Two or More <-50 0.628 1 0.628 0.682 0.644 I

TBVOOS i f"l%

  • 50 0.566 1 0.566 0.594 1 I - I - 1 0.990 1

I 50

-PROOS 0.554 0.554 0.554 0.554 0.554 0.702 0.742 0.990 DLO 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 Fuels DOC ID: COLR Clinton I Rev. 9 CLI C15 Core Operating Limits Report Non-Proprietary Information Submitted in Accordance with 10 CFR 2.390 Table 5-8 Flow Dependent LHGR Multiplier LHGRFAC(F) for Base Case/PROOS (Loss of 'FULL' Feedwater Heating)'

(Reference 3)

Core Flow LHGRFAC(F)

(% rated) ________F 0.0 0.438 25.0 0.606 30.0 0.640 82.2 0.990 109.0 0.990 Table 5-9 Flow 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 0.139 25.0 0.361 30.0 0.406 40.0 0.495 50.0 0.624 80.0 0.851 98.3 0.990 109.0 0.990

'Linear interpolation should be used for points not listed in the table.

Page 22 of 58

Exelon Nuclear - Nuclear Fuels DOC ID: COLR Clinton I Rev. 9 CLIC15 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) 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 3.7.6 7.2

Description:

The operability requirements for the Main Turbine Bypass System are governed by Technical Specification 3.7.6. Ifthe requirements of LCO 3.7.6 cannot be met, the appropriate reactor thermal power, minimum critical power ratio (MCPR), and linear heat generation rate (LHGR) limits must be used to comply with the assumptions in the design basis transient analysis.

Table 7-1 provides the reactor thermal power limitations for an inoperable Main Turbine Bypass System as specified in Technical Specification 3.7.6 action statement A.1. The MCPR and LHGR limits for one TBVOOS are included in the Base Case for Cycle 15, as identified in Table 9-1. The MCPR and LHGR limits for two or more TBVOOS are provided in Sections 4 and 5.

Table 7-1 Reactor Power Limitation - Turbine Bypass Valves Out of Service (References 2 and 3)

Turbine Bypass System Status J Maximum Reactor Thermal Power (% Rated)

One Turbine Bypass Valve 100.0 Out of Service Two or More Turbine Bypass Valves 97.0 Out of Service 97.0 Page 23 of 58

Exelon Nuclear - Nuclear Fuels DOC ID: COLR Clinton I Rev. 9 CLIC15 Core Operating Limits Report Non-Proprietary Information Submitted in Accordance with 10 CFR 2.390 8.0 Stability Protection Setpoints 8.1 Technical Specification

Reference:

Section 3.3.1.3 8.2

Description:

The Clinton 1 Cycle 15 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 and 8-2. 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 (Valid for All Conditions)

(Reference 3)

P Corresponding Maximum Confirmation PBDA Trip Amplitude Count Trip Setting 1.10 1 13 Table 8-2 OPRM PBDA Trip Setpoints - SLO1 (Valid for SLO Conditions Only)

(Reference 3)

PBDATripAmpltud Corresponding Maximum Confirmation PBDATripAmpltudeCount Trip Setting 1.15 16 Notes for Table 8-2:

1. The standard two loop operation OPRM Trip Setpoints specified in Table 8-1 must be implemented prior to restarting the idle pump when exiting the SLO condition.

Page 24 of 58

Exelon Nuclear - Nuclear Fuels DOC ID: COLR Clinton 1 Rev. 9 CLIC15 Core Operating Limits Report Non-Proprietary Information Submitted in Accordance with 10 CFR 2.390 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)

_____________O _____p_ Operating Region EOOS Options 2 Standard MELLLA ICF ] FFWTR1 ] Coastdown Base Case DLO 3 Yes Yes Yes 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 Two or More TBVOOS DLO 4 Yes Yes Yes Yes Yes Two or More TBVOOS SLO' 4 Yes No No No Yes Notes:

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 been evaluated 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 in cycle operation in Dual Loop mode.
4. Includes 2 SRVOOS, 1 ADSOOS, and up to a 50TF feedwater temperature reduction (FWTR includes feedwater heater OOS 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. 9 CLIC15 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 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 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. GE Hitachi Nuclear Energy Report, 0000-0086-4634-R2-P, "Clinton Power Station One Bypass Out of Service or Turbine Bypass System out of Service Analysis - Final", July 2010.
3. Global Nuclear Fuel Document, 0000-0154-8722-SRLR Revision 0, "Supplemental Reload Licensing 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 Clinton Power Station", February 2002.
6. Exelon Transmittal of Design Information, TODI ES1300006 Revision 0, "Resolved OPL-3 Parameters for Clinton Cycle 15", May 9, 2013.
7. GE Hitachi Nuclear Energy Letter, CFL-EXN-LH1-12-059, "Affirmation of the Clinton Power Station 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 With Equipment 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 Power Station", February 2015.

Page 26 of 58

Exelon Nuclear - Nuclear Fuels DOC ID: COLR Clinton I Rev. 9 CLIC15 Core Operating Limits Report Non-Proprietary Information Submitted in Accordance with 10 CFR 2.390 Appendix A Page 27 of 58

Exelon Nuclear - Nuclear Fuels CLIC15 Core Operating Uimits Report DOC ID: COLR Clinton I Rev. 9 I Non-Proprietary Infornation Submitted in Accordance with 10 CFR 2.390 GNF. Global Nuclear Fuel Global Nuclear Fuel A Joint Venture of GE,Toshiba. & Hitachi 0000-0154-8722-FBIR-NP Revision 0 Class I August 2013 Non-ProprietaryInformation - Class I (Public)

Fuel Bundle Information Report for Clinton Power Station Unit 1 Reload 14 Cycle 15 Copyright 2013 Global Nuclear Fuel - Americas, LLC All Rights Reserved Page 28 of 58

Exelon Nuclear - Nuclear Fuels DOC ID: COLR Clinton I Rev. 9 I CLIC15 Core Operating Uimits Report Non-Proprietary Information Submitted in Accordance with 10 CFR 2.390 Clinton Non-Proprietary Information 0000-01 54-8722-FBIR-NP Reload 14 - Class I (Public) 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 known 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 0000-0154-8722-FBIR-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 ((

Page 2 Page 29 of 58

Exelon Nuclear - Nuclear Fuels DOC ID: COLR Clinton I Rev. 9 I CLIC15 Core Operating Umits Report Non-Proprietary Information Submitted in Accordance with 10 CFR 2.390 Clinton Non-Proprietary Information 0000-01 54-8722-FBIR-NP R~Inocd 14

- Class I (Public) Revision 0 Reload 14

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 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 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-I 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 3 Page 30 of 58

Exelon Nuclear - Nuclear Fuels DOC ID: COLR Clinton I Rev. 9 I CLIC15 Core Operating Umits Report Non-Proprietary Information Submitted in Accordance with 10 CFR 2.390 Clinton Non-Proprietary Information 0000-01 54-8722-FBIR-NP Reload 14 - Class I (Public) Revision 0

2. References
1. General Electric StandardApplication for Reactor Fuel, NEDE-2401 I-P-A- 19, May 2012; and the U.S. Supplement, NEDE-2401 1-P-A-19-US, May 2012.

Page 4 Page 31 of 58

Exelon Nuclear - Nuclear Fuels DOC ID: COLR Clinton I Rev. 9 I CLIC15 Core Operating ULmits Report Non-Proprietary Informaflon Submitted in Accordance with 10 CFR 2.390 Clinton Non-Proprietary Information 0000-0154-8722-FBIR-NP D =1-.

  • A 1 A - Class I (Ptbiheic Revision 0

- Class I (Public) Revision 0 Appendix A UO 21Gd Thermal-Mechanical LHGR Limits Bundle Type: GEl 4-P 0OSNAB4I 8-15GZ-120T-150-T6-3240 (GE14C)

Bundle Number: 3240 Peak Pellet Exposure U0 2 LHGR Limit GWd/MT (GWd/ST) kW/ft Er Peak Pellet Exposure Most Limiting Gadolinia LHGR Limit' GWd/MT (GWd/ST) kW/ft

[r Bounding gadolinia LHGR limit for all gadolinium concentrations occurring in this bundle design Er )).

Page 5 Page 32 of 58

Exelon Nuclear - Nuclear Fuels DOC ID: COLR Clinton I Rev. 9 I CLI C15 Core Operating Limits Report Non-Proprietary Information Submitted in Accordance with 10 CFR 2.390 Clinton Non-Proprietary Information 0000-01 54-8722-FBIR-NP Reload 14 - Class I (Public) Revision 0 UO 2 /Gd Thermal-Mechanical LHGR Limits Bundle Type: GE 141-P IOSCOB405-13 GZ-120T-150-T6-3243 (GE 141)

Bundle Number: 3243 Peak Pellet Exposure U0 2 LHGR Limit GWd/MT (GWd/ST) kW/ft

((i Peak Pellet Exposure Most Limiting Gadolinia LHGR Limit 2 GWd/MT (GWd/ST) kW/ft

((_____________________

2 BoUnding gadolinia LHGR limit foi all gadolinium concettrations occurring in this bundle design Page 6 Page 33 of 58

Exelon Nuclear - Nuclear Fuels DOC ID: COLR Clinton I Rev. 9 I CLIC15 Core Operating Uimits Report Non-Proprietary Information Submitted in Accordance with 10 CFR 2.390 Clinton Non-Proprietary Information 0000-0 154-8722-FBIR-NP Reload 14 - Class I (Public) Revision 0 UO21Gd Thermal-Mechanical LHGR Limits Bundle Type: GEI4-PIOSNAB418-15GZ-120T-150-T6-3242 (GEI4C)

Bundle Number: 3242 Peak Pellet Exposure U0 2 LHGR Limit GWd/MT (GWd/ST) kW/ft Peak Pellet Exposure Most Limiting Gadolinia LHGR Limit 3 GWd/MT (GWd/ST) kW/ft

((l

_______________________________ ))

Bounding gadolinia LHGR limit for all gadolinium concentrations occurring in this bundle design

(( ))

Page 7 Page 34 of 58

Exelon Nuclear - Nuclear Fuels DOC ID: COLR Clinton I Rev. 9 I CLIC15 Core Operating Limits Report Non-Proprietary linformation Submitted in Accordance with 10 CFR 2.390 Clinton Non-Proprietary Infonnation 0000-01 54-8722-FBIR-NP Reload 14 - Class I (Public) Revision 0 UQ2IGd Thermal-Mechanical LHGR Limits Bundle Type: GE 14-P I OSNAB422-13GZ- 120T- 150-T6-3239 (GE 14C)

Bundle Number: 3239 Peak Pellet Exposure U0 2 LHGR Limit GWd/MT (GWd/ST) kW/ft Peak Pellet Exposure Most Limiting Gadolinia LHGR Limit 4 GWd/MT (GWd/ST) kW/ft

((I___________________

4 Bounding gadolinia L1-GR limit for all gadolinium concentrations occurring in this bundle design Page 8 Page 35 of 58

Exelon Nuclear - Nuclear Fuels DOC ID: COLR Clinton I Rev. 9 I CLIC15 Core Operating Uimits Report Non-Proprietary Information Submitted in Accordance with 10 CFR 2.390 Clinton Non-Proprietary Information 0000-01 54-8722-FBIR-NP Reload 14 - Class I (Public) Revision 0 UO2 1Gd Thermal-Mechanical LHGR Limits Bundle Type: GEl 4-P I OSNAB418-15GZ- 120T- 150-T6-3241 (GE I4C)

Bundle Number: 3241 Peak Pellet Exposure U0 2 LHGR Limit GWd/MT (GWd/ST) kW/ft Er Peak Pellet Exposure Most Limiting Gadolinia LHGR Limit' GWd/MT (GWd/ST) kW/ft Er 5 Bounding gadolinia LHGR limit for all gadolinium concentrations occurring in this bundle design

(( I].

Page 9 Page 36 of 58

Exelon Nuclear- Nuclear Fuels DOC ID: COLR Clinton I Rev. 9 I CLIC15 Core Operating Limits Report Non-Proprietary Information Submitted in Accordance with 10 CFR 2.390 Clinton Non-Proprietary Information 0000-0 154-8722-FBIR-NP Reload 14 - Class I (Puhlic') Revision 0 UQ2IGd Thermal-Mechanical LHGR Limits Bundle Type: GNF2-PI 0SG2B402-15GZ- 120T2-150-T6-4009 (GNF2)

Bundle Number: 4009 Peak Pellet Exposure UOz LHGR Limit GWd/MT (GWd/ST) kW/ft

((

Peak Pellet Exposure Most Limiting Gadolinia LHGR Limit 6 GWd/MT (GWd/ST) kW/ft

((

_______________________________ ))

,Bounding gadolinia LHGR limit for all gadolinium concentrations occurring in this bundle design Page 10 Page 37 of 58

Exelon Nuclear - Nuclear Fuels DOC ID: COLR Clinton I Rev. 9 1 CLIC15 Core Operating Umits Report Non-Proprietary Information Submitted in Accordance with 10 CFR 2.390 Clinton Non-Proprietary Information 0000-01 54-8722-FBIR-NP Reload 14 - Class I (PIiblic) Revision 0 UO 21Gd Thermal-Mechanical LHGR Limits Bundle Type: GNF2-P 10SG2B401-15GZ- 120T2-150-T6-4010 (GNF2)

Bundle Number: 4010 Peak Pellet Exposure U0 2 LHGR Limit GWd/MT (GWd/ST) kW/ft

((I Peak Pellet Exposure Most Limiting Gadolinia LHGR Limit 7 GWd/MT (GWd/ST) kW/ft R[

Bounding gadolinia LHGR limit for all gadolinium concentrations occurring in this bundle design

((i )).

Page 11 Page 38 of 58

Exelon Nuclear - Nuclear Fuels DOC ID: COLR Clinton I Rev. 9 I CLIC15 Core Operating Umits Report Non-Proprietary Information Submitted in Accordance with 10 CFR 2.390 Clinton Non-Proprietary Information 0000-0 1 54-8722-FBIR-NP Rolný r 1A - Class I (Puthlic Revision (1

- Class I (Public) Revision 0 UO 2lGd Thermal-Mechanical LHGR Limits Bundle Type: GNF2-P 1OSG2B402-12G7.0-120T2-150-T6-401 I (GNF2)

Bundle Number: 4011 Peak Pellet Exposure U0 2 LHGR Limit GWd/MT (GWd/ST) kW/ft

((

Peak Pellet Exposure Most Limiting Gadolinia LHGR Limit 8 GWd/MT (GWd/ST) kW/ft Er

________________________________I))

Bounding gadolnia LHGR liiiii for all gadolinium concentrations occunring in this bundle design Page 12 Page 39 of 58

Exelon Nuclear - Nuclear Fuels DOC ID: COLR Clinton I Rev. 9 I CLIC15 Core Operating Umits Report Non-Proprietary Information Submitted in Accordance with 10 CFR 2.390 Clinton Non-Proprietary Information 0000-01 54-8722-FBIR-NP Reload 14 - Class I (Public) Revision 0 UO21Gd Thermal-Mechanical LHGR Limits Bundle Type: GNF2-P I 0SG2B402-14GZ- 120T2-150-T6-4012 (GNF2)

Bundle Number: 4012 Peak Pellet Exposure U0 2 LHGR Limit GWd/MT (GWd/ST) kW/ft I((

Peak Pellet Exposure Most Limiting Gadolinia LHGR Limit 9 GWd/MT (GWd/ST) kW/ft

[II 9 Bounding gadolinia LHGR limit lbr all gadolinium concentrations occurring in this bundle design Page 13 Page 40 of 58

Exelon Nuclear- Nuclear Fuels DOC ID: COLR Clinton I Rev. 9 I CLIC15 Core Operating Umits Report Non-Proprietary Information Submitted in Accordance with 10 CFR 2.390 Clinton Non-Proprietary Infornation 0000-01 54-8722-FBIR-NP Reload 14 - Class I (Public) Revision 0 UO 2/Gd Thermal-Mechanical LHGR Limits Bundle Type: GNF2-PI 0SG2B383-14GZ- 120T2-150-T6-4252 (GNF2)

Bundle Number: 4252 Peak Pellet Exposure UO 2 LHGR Limit GWd/MT (GWd/ST) kW/ft

((

Peak Pellet Exposure Most Limiting Gadolinia LHGR Limit' 0 GWd/MT (GWd/ST) kW/ft

((

_______________________________ ))

"0 Bounding gadolinia LHGR limit lor all gadolinium concentrations occurring in this bundle design Er R].

Page 14 Page 41 of 58

Exelon Nuclear - Nuclear Fuels DOC ID: COLR Clinton I Rev. 9 I CLIC15 Core Operating Umits Report Non-Proprietary Information Submitted in Accordance with 10 CFR 2.390 Clinton Non-Proprietary Information 0000-01 54-8722-FBIR-NP Reload 14 - Class I (Public) Revision 0 UO 21Gd Thermal-Mechanical LHGR Limits Bundle Type: GNF2-P I 0SG2B384-l4GZ- 120T2-150-T6-4253 (GNF2)

Bundle Number: 4253 Peak Pellet Exposure U0 2 LHGR Limit GWd/MT (GWd/ST) kW/ft E[

Peak Pellet Exposure Most Limiting Gadolinia LHGR Limit' 1 GWd/MT (GWd/ST) kW/ft Er

_____________________________ ))

Bounding gadolinia L1-GR limit lbr all gadolinium concentrations occurring in this bundle design Page 15 Page 42 of 58

Exelon Nuclear - Nuclear Fuels DOC ID: COLR Clinton I Rev. 9 I CLIC15 Core Operating Limits Report Non-Proprietary Information Submitted in Accordance with 10 CFR 2.390 Clinton Non-Proprietary Information 0000-01 54-8722-FBIR-NP Reload 14 - Class I (Piuhlip.c Revision 0 Reload 14 U0 2/Gd Thermal-Mechanical LHGR Limits Bundle Type: GNF2-P I 0SG2B383-14GZ- 120T2-150-T6-4254 (GNF2)

Bundle Number: 4254 Peak Pellet Exposure U0 2 LHGR Limit GWd/MT (GWd/ST) kW/ft Peak Pellet Exposure Most Limiting Gadolinia LHGR Limit' 2 GWd/MT (GWd/ST) kW/ft Er 12 Bounding gadoiinia LHGR limit for ail gadolinium concentrations occurring in this bundle design Page 16 Page 43 of 58

Exelon Nuclear - Nuclear Fuels DOC ID: COLR Clinton I Rev. 9 1 CLIC15 Core Operating Umits Report Non-Proprietary Information Submitted in Accordance with 10 CFR 2.390 Clinton Non-Proprietary Information 0000-01 54-8722-FBIR-NP Reload 14 - Class T(Puhlic) Revision 0 UO 21Gd Thermal-Mechanical LHGR Limits Bundle Type: GNF2-P I 0SG2B396-12G5.0-120T2-150-T6-4255 (GNF2)

Bundle Number: 4255 Peak Pellet Exposure U0 2 LHGR Limit GWd/MT (GWd/ST) kW/ft Peak Pellet Exposure Most Limiting Gadolinia LHGR Limit ,3 GWd/MT (GWd/ST) kW/ft Er

'3 Bounding gadolinia LHGR limit for all gadolinium concentrations occurring in this bundle design

(( ]1.

Page 17 Page 44 of 58

Exelon Nuclear - Nuclear Fuels DOC ID: COLR Clinton I Rev. 9 I CLIC15 Core Operating Limits Report Non-Proprietary Information Submitted in Accordance with 10 CFR 2.390 Clinton Non-Proprietary Information 0000-01 54-8722-FBIR-NP Reload 14 - Class I (Piihlic) Revision 0 Appendix B Fuel Bundle Information Table B-I Bundle Specific Information Bundle Enrichment Weight Weight Max Exposure Fuel of UO 2 ofU k- 0at at Max kT Bundle Number (wt% U-235) 20 C GWd/MT (kg) (kg) i~ (GWd/ST)

GE14-P 1OSNAB418-15GZ-120T- 150-T6-3240 (GE 14C)

GEI41-PIOSCOB405-13GZ- 3243 120T-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- 3241 120T-150-T6-3241 (GE14C)

GNF2-P I 0SG2B402-15GZ-120T2-150-T6-4009 (GNF2)

GNF2-P IOSG2B401-15GZ-120T2-150-T6-4010 (GNF2)

GNF2-P 10SG2B402-12G7.0- 4011 120T2-150-T6-4011 (GNF2)

GNF2-P 10SG2B402-14GZ-120T2-150-T6-4012 (GNF2)

GNF2-P l 0SG2B3383-14GZ-120T2-150-T6-4252 (GNF2)

GNF2-P I0SG2B384-14GZ-120T2-150-T6-4253 (GNF2)

GNF2-P10SG2B383-14GZ-120T2-150-T6-4254 (GNF2)

GNF2-P10SG2B396-12G5.0- 4255 120T2-150-T6-4255 (GNF2) 14 Maximum lattice k. for the most reactive uncontrolled state plus a (( )) adder for uncertainties.

Page 18 Page 45 of 58

Exelon Nuclear - Nuclear Fuels DOC ID: COLR Clinton I Rev. 9 I CLIC15 Core Operating ULmits Report Non-Proprietary Information Submitted in Accordance with 10 CFR 2.390 Clinton Non-Proprietary Information 0000-01 54-8722-FBIR-NP Reload 14 - Class I (Public) Revision 0 11l Figure B-1 Enrichment and Gadolinium Distribution for EDB No. 3240 Fuel Bundle GEI4-PIOSNAB418-15GZ-120T-150-T6-3240 (GEI4C)

Page 19 Page 46 of 58

Exelon Nuclear - Nuclear Fuels DOC ID: COLR Clinton I Rev. 9 I CLIC15 Core Operating ULmits Report Non-Proprietary infrmation Submitted in Accordance with 10 CFR 2.390 Clinton Non-Proprietary Information 0000-01 54-8722-FBIR-NP Reload 14 - Class I (Public) Revision 0 Figure B-2 Enrichment and Gadolinium Distribution for EDB No. 3243 Fuel Bundle GEl41-PIOSCOB405-13GZ-120T-I50-T6-3243 (GEl41)

Page 20 Page 47 of 58

Exelon Nuclear - Nuclear Fuels DOC ID: COLR Clinton I Rev. 9 I CLIC15 Core Operating Umits Report Non-Proprietary Infornation Submitted in Accordance with 10 CFR 2.390 Clinton Non-Proprietary Information 0000-01 54-8722-FBIR-NP Reload 14 - Class I (Public) Revision 0

((

1]

Figure B-3 Enrichment and Gadolinium Distribution for EDB No. 3242 Fuel Bundle GE14-P1OSNAB418-15GZ-120T-150-T6-3242 (GE14C)

Page 21 Page 48 of 58

Exelon Nuclear - Nuclear Fuels DOC ID: COLR Clinton I Rev. 9 I CLIC15 Core Operating Umits Report Non-Proprietary Information Submitted in Accordance with 10 CFR 2.390 Clinton Non-Proprietary Information 0000-01 54-8722-FBIR-NP Reload 14 - Class I (Public) Revision 0

((

Figure B-4 Enrichment and Gadolinium Distribution for EDB No. 3239 Fuel Bundle GEl 4-PI OSNAB422-13GZ-1 20T-150-T6-3239 (GEl 4C)

Page 22 Page 49 of 58

Exelon Nuclear - Nuclear Fuels DOC ID: COLR Clinton I Rev. 9 I CLIC15 Core Operating Umits Report Non-Proprietary Information Submitted in Accordance with 10 CFR 2.390 Clinton Non-Proprietary Information 0000-0154-8722-FBIR-NP Reload 14 - Class I (Public) Revision 0

((

Figure B-5 Enrichment and Gadolinium Distribution for EDB No. 3241 Fuel Bundle GEl 4-Pt OSNAB418-15GZ-1 20T-1 50-T6-3241 (GE14C)

Page 23 Page 50 of 58

Exelon Nuclear - Nuclear Fuels DOC ID: COLR Clinton I Rev. 9 I CLIC15 Core Operating Umits Report Non-Proprietary Information Submitted in Accordance with 10 CFR 2.390 Clinton Non-Proprietary Information 0000-01 54-8722-FBIR-NP Reload 14 - Class I (Public) Revision 0

((

Figure B-6 Enrichment and Gadolinium Distribution for EDB No. 4009 Fuel Bundle GNF2-P1OSG2B402-15GZ-120T2-150-T6-4009 (GNF2)

Page 24 Page 51 of 58

Exelon Nuclear - Nuclear Fuels DOC ID: COLR Clinton I Rev. 9 I CLIC15 Core Operating Umits Report Non-Proprietary Informnation Submitted in Accordance with 10 CFR 2.-g0 Clinton Non-Proprietary Information 0000-01 54-8722-FBIR-NP Reload 14 - Class I (Public) Revision 0

((

Figure B-7 Enrichment and Gadolinium Distribution for EDB No. 4010 Fuel Bundle GNF2-P1OSG2B401-15GZ-120T2-150-T6-4010 (GNF2)

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Exelon Nuclear - Nuclear Fuels DOC ID: COLR Clinton I Rev. 9 I CLIC15 Core Operating Umits Report Non-Proprietary Information Submitted in Accordance with 10 CFR 2.390 Clinton Non-Proprietary Information 0000-01 54-8722-FBIR-NP R *lnacl 14

- Class I (Public) Revision 0 Reload 14 Figure B-8 Enrichment and Gadolinium Distribution for EDB No. 4011 Fuel Bundle GNF2-PIOSG2B402-12G7.0-120T2-150-T6-4011 (GNF2)

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Exelon Nuclear - Nuclear Fuels DOC ID: COLR Clinton I Rev. 9 I CLIC15 Core Operating Uimits Report Non-Proprietary Information Submitted in Accordance with 10 CFR 2.390 Clinton Non-Proprietary Information 0000-0154-8722-FBIR-NP Reload 14 - Class I (Public) Revision 0 11l

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Figure B-9 Enrichment and Gadolinium Distribution for EDB No. 4012 Fuel Bundle GNF2-PIOSG2B402-14GZ-120T2-150-T6-4012 (GNF2)

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Exelon Nuclear- Nuclear Fuels DOC ID: COLR Clinton I Rev. 9 I CLIC15 Core Operating Umits Report Non-Proprietary Information Submitted in Accordance with 10 CFR 2.390 Clinton Non-Proprietary Information 0000-0154-8722-FBIR-NP Reload 14 - Class I (Public) Revision 0

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Figure B-10 Enrichment and Gadolinium Distribution for EDB No. 4252 Fuel Bundle GNF2-PIOSG2B383-14GZ-120T2-150-T6-4252 (GNF2)

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Exelon Nuclear - Nuclear Fuels DOC ID: COLR Clinton I Rev. 9 I CLIC15 Core Operating Umits Report Non-Proprietary Information Submitted in Accordance with 10 CFR 2.390 Clinton Non-Proprietary Information 0000-01 54-8722-FBIR-NP Reload 14 - Class I (Pubhlic') Revision 0I Reload 14 - Class I (PUblic) Revision 0

[Ii Figure B-1 I Enrichment and Gadolinium Distribution for EDB No. 4253 Fuel Bundle GNF2-PIOSG2B384-14GZ-120T2-150-T6-4253 (GNF2)

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Exelon Nuclear - Nuclear Fuels DOC ID: COLR Clinton I Rev. 9 I CLIC15 Core Operating Umits Report Non-Proprietary Information Submitted in Accordaice with 10 CFR 2.390 Clinton Non-Proprietary Information 0000-01 54-8722-FBIR-NP RPl1-,A I1A - Class I (Public) Revision 0

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Figure B-12 Enrichment and Gadolinium Distribution for EDB No. 4254 Fuel Bundle GNF2-PIOSG2B383-14GZ-120T2-150-T6-4254 (GNF2)

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Exelon Nuclear - Nuclear Fuels DOC ID: COLR Clinton I Rev. 9 I CLIC15 Core Operating Umits Report Non-Proprietary Information Submitted in Accordance with 10 CFR 2.390 Clinton Non-Proprietary Information 0000-01 54-8722-FBIR-NP Reload 14 - Class I (Puhlic) Revision 0

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Figure B-13 Enrichment and Gadolinium Distribution for EDB No. 4255 Fuel Bundle GNF2-PIOSG2B396-12G5.0-120T2-150-T6-4255 (GNF2)

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