ML11265A046: Difference between revisions
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FFWTR Final Feedwater Temperature Reduction. | 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 adjustments and multipliers LHGRFAC(P) | FWHOOS Feedwater Heaters Out of Service ICF Increased Core Flow LHGR Linear Heat Generation Rate LHGRFAC(F), LHGR thermal limit flow dependent adjustments and multipliers LHGRFAC(P) | ||
LHGR thermal limit power dependent adjustments and, multipliers MAPLHGR Maximum Average Planar Linear Heat Generation Rate MCPR Minimum Critical Power Ratio MCPR(P) MCPR thermal limit power dependent adjustments and multipliers MCPR(F) MCPR thermal limit flow dependent adjustments and multipliers OLMCPR Operating Limit Minimum Critical Power Ratio OPRM Oscillation Power Range Monitor SLMCPR Safety Limit Minimum Critical Power Ratio SLO Single Reactor Recirculation Loop Operation TBSOOS Turbine Bypass System Out of Service 1TBVOOS One Turbine Bypass Valve Out of Service Page.4 of 57 Exelon Nuclear -Nuclear Fuels DOC ID: COLR Clinton I Rev. 5 CLL C13 Core Operating Limits Report Non-Proprietary Information Submitted in Accordance with 10 CFR 2.390 2.0 General Information This repoit is prepared in accordance with Technical Specificationr 5.6.5 of Reference | LHGR thermal limit power dependent adjustments and, multipliers MAPLHGR Maximum Average Planar Linear Heat Generation Rate MCPR Minimum Critical Power Ratio MCPR(P) MCPR thermal limit power dependent adjustments and multipliers MCPR(F) MCPR thermal limit flow dependent adjustments and multipliers OLMCPR Operating Limit Minimum Critical Power Ratio OPRM Oscillation Power Range Monitor SLMCPR Safety Limit Minimum Critical Power Ratio SLO Single Reactor Recirculation Loop Operation TBSOOS Turbine Bypass System Out of Service 1TBVOOS One Turbine Bypass Valve Out of Service Page.4 of 57 Exelon Nuclear -Nuclear Fuels DOC ID: COLR Clinton I Rev. 5 CLL C13 Core Operating Limits Report Non-Proprietary Information Submitted in Accordance with 10 CFR 2.390 2.0 General Information This repoit is prepared in accordance with Technical Specificationr 5.6.5 of Reference | ||
: 1. P0wer 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 Reference 2 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: | : 1. P0wer 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 Reference 2 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 | * 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 at any time during the cycle prior to cycle extension. | -.,* Feedwater Heater Out of Service (FWHOOS) up to 50°F feedwater temperature reduction at any time during the cycle prior to cycle extension. | ||
The Clinton Unit 1 Cycle 13 COLR was revised mid-cycle (Revision | The Clinton Unit 1 Cycle 13 COLR was revised mid-cycle (Revision | ||
: 5) under EC 380905 to support operation with 1TBVOOS or TBSOOS. The changes are indicated by revision bars in the right hand margin. It should be noted that the MCPR(F) values-for the 0.000% core flow point in Tables 4-5 and 4-6 are different than those specified in References 3 and 6. The difference is due to References 3 and 6 truncating/rounding the value to two (2) significant digits. The Values presented in Tables 4-5 and 4-6 are in agreement with the databank thermal limit set and are conservative. | : 5) under EC 380905 to support operation with 1TBVOOS or TBSOOS. The changes are indicated by revision bars in the right hand margin. It should be noted that the MCPR(F) values-for the 0.000% core flow point in Tables 4-5 and 4-6 are different than those specified in References 3 and 6. The difference is due to References 3 and 6 truncating/rounding the value to two (2) significant digits. The Values presented in Tables 4-5 and 4-6 are in agreement with the databank thermal limit set and are conservative. | ||
Page"s'of 57 Exelon Nuclear -Nuclear Fuels CLIC13 Core Operating Limits Report Non-Proprietary Information Submitted in Accordance with 10 CFR 2.390 DOC ID: COLR Clinton I Rev. 5 3.0 MAPLHGR Limits 3.1 Technical Specification | Page"s'of 57 Exelon Nuclear -Nuclear Fuels CLIC13 Core Operating Limits Report Non-Proprietary Information Submitted in Accordance with 10 CFR 2.390 DOC ID: COLR Clinton I Rev. 5 3.0 MAPLHGR Limits 3.1 Technical Specification | ||
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The various MCPR limits are described below.4.2.1 Manual Flow Control MCPR Limits The Operating Limit MCPR (OLMCPR) is determined from either section 4:2.1.1 or 4.2.1.2, whichever is greater at any given power and flow condition' 4.2.1.1 Power-Dependent MCPR For operation less than or equal to 33.3% core thermal power, the MCPR(P) as a function of core thermal power is shown in Table 4-2. For .operation at greater than 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.The Base Case (DLO and SLO) MCPR(P) and K(P) given in Table 4-2 are also applicable to the corresponding condition with 1TBVOOS or TBSOOS (References 3 and 6).4.2.1.2 Flow-Dependent MCPR Tables 4-3 through 4-6 give the MCPR(F) as a function of flow based on the applicable plant condition. | The various MCPR limits are described below.4.2.1 Manual Flow Control MCPR Limits The Operating Limit MCPR (OLMCPR) is determined from either section 4:2.1.1 or 4.2.1.2, whichever is greater at any given power and flow condition' 4.2.1.1 Power-Dependent MCPR For operation less than or equal to 33.3% core thermal power, the MCPR(P) as a function of core thermal power is shown in Table 4-2. For .operation at greater than 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.The Base Case (DLO and SLO) MCPR(P) and K(P) given in Table 4-2 are also applicable to the corresponding condition with 1TBVOOS or TBSOOS (References 3 and 6).4.2.1.2 Flow-Dependent MCPR Tables 4-3 through 4-6 give the MCPR(F) as a function of flow based on the applicable plant condition. | ||
The limits for dual.loop operationarelisted in Table 4-3. The limits for single loop operation are listed in Table 4-4. The limits for dual loop operation with 1TBVOOS or TBSOOS are listed in Table 4-5. The limits for single loop operation with 1TBVOOS or TBSOQS arelisted in Table 4-6'. The MCPR(F) determined from these tables is the flow dependent OLMCPR.4.2.2 Automatic Flow Control MCPR Limits Automatic Flow Control MCPR Limits are not provided.,Page.7 of 57 Exelon Nuclear -.Nuclear Fuels DOC ID: COLR Clinton I Rev. 5 CLLC13 Core Operating Limits Report Non-Proprietary Information Submitted in Accordance with 10 CFR 2.390 4.2.3 Option A and Option B Option A and Option B refer to use of scram speeds for establishing MCPR operating limits.Option A scram speed is the BWR/6 Technical Specification scram speed. The Technical Specification scram speeds must be met to utilize the Option A MCPR limits. Reload analyses. | The limits for dual.loop operationarelisted in Table 4-3. The limits for single loop operation are listed in Table 4-4. The limits for dual loop operation with 1TBVOOS or TBSOOS are listed in Table 4-5. The limits for single loop operation with 1TBVOOS or TBSOQS arelisted in Table 4-6'. The MCPR(F) determined from these tables is the flow dependent OLMCPR.4.2.2 Automatic Flow Control MCPR Limits Automatic Flow Control MCPR Limits are not provided.,Page.7 of 57 Exelon Nuclear -.Nuclear Fuels DOC ID: COLR Clinton I Rev. 5 CLLC13 Core Operating Limits Report Non-Proprietary Information Submitted in Accordance with 10 CFR 2.390 4.2.3 Option A and Option B Option A and Option B refer to use of scram speeds for establishing MCPR operating limits.Option A scram speed is the BWR/6 Technical Specification scram speed. The Technical Specification scram speeds must be met to utilize the Option A MCPR limits. Reload analyses. | ||
performed by GNF for.Cycle,13 Option A.MCPR limits utilized a 20% core average insertion time of 0.516 seconds (Reference 12).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 | performed by GNF for.Cycle,13 Option A.MCPR limits utilized a 20% core average insertion time of 0.516 seconds (Reference 12).To utilize the MCPR limits for the Option B scram speed, the cycle average scram insertion time for 20% insertion must satisfy equation 2 in Reference 5.Section | ||
: 4. If the cycle average scram insertion time does not meet the Option B criteria, the appropriate MCPR value may be determined from a linear interpolation between the Option A and B limits as specified by equation 4 in Reference 5 Section 4.4.2.4 Recirculation Flow Control Valve Settings Cycle 13 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 11).Page 8 of 57 Exelon Nuclear- Nuclear Fuels CLL C13 Core Operating Limits Report Non-Proprietary Information Submitted in Accordance with 10 CFR 2.390 DOC ID: COLR Clinton 1 Rev. 5 Table 4-1 Operating Limit Minimum Critical Power Ratio" '(Reference 3)EOS. GE14C Fuel GE14CFuel | : 4. If the cycle average scram insertion time does not meet the Option B criteria, the appropriate MCPR value may be determined from a linear interpolation between the Option A and B limits as specified by equation 4 in Reference 5 Section 4.4.2.4 Recirculation Flow Control Valve Settings Cycle 13 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 11).Page 8 of 57 Exelon Nuclear- Nuclear Fuels CLL C13 Core Operating Limits Report Non-Proprietary Information Submitted in Accordance with 10 CFR 2.390 DOC ID: COLR Clinton 1 Rev. 5 Table 4-1 Operating Limit Minimum Critical Power Ratio" '(Reference 3)EOS. GE14C Fuel GE14CFuel | ||
.GE141 Fuel GE141 Fuel C Option B .Option A; Option B Option A Combination All exposures All-exposures All exposures All exposures Base Case DLO 1.291 1:35 1.36 1.42 Base Case SLO 2' 1.32 1.38 1.39 1.45 1TBVOOS DLO 1.291 1.35 1.36 1.42 1TBVOOS SLO 2 1.32 1.38 1.39 1.45 TBSOOS DLO 1.30 1.40 1.37 1.47 TBSOOS SLO 2 1.33 1.43 1.40 1.50 Notes for Table 4-1: 1. Analyzed DLO Option B OLMCPR is 1.27 per Reference 3, value is adjusted to obtain an OPRM amplitude setpoint of 1.10.2. SLO Option A(B) OLMCPR is the DLO Option A(B) OLMCPR plus 0.03.Page,9of 57 Exelon Nuclear -Nuclear Fuels CLIC13 Core Operating Limits Report Non-Proprietary Information Submitted in Accordance with 10 CFR 2.390 DOC ID:. COLR Clinton 1. Rev. 5..Table 4-2 Power Dependent MCPR Limits" MCPR(P) and Multipliers K(P)1 2 (References 3 and 7)EQOS Core Flow -Core Thermal Power (%)Combito (% of 0 121.6 <S33.3 >33.3 1<43 >431 <70 >70 100 Rated) _ MCPR(P) .I.. -.. .. K(P)3 Base Case DLO <_50 2.20 2.20 1.97 1.351 1.347 1.313 1.212 1.15 1.00 GE14C > 50 2.46 2.46 2.17 Base Case SLO <_50 2.23 2.23 2.00 1:351 1.347 1.313 1.212 1.15 1.00 GE14C > 50 2.49 2.49 2.20 Base Case DLO < 50 2.27 2.27 2.04 1.351 1.347 1.313 1.212 1.15 1.00 GE141 > 50 2.53 2.53 2.24 Base Case SLO < 50 2.30 2.30 2.07 1.351... 1.347 .1.313 1.212 1.15 1.00 GE141 > 50 2.56 2.56 2.271 Notes for Table 4-2: 1. Values are interpolated between relevant power levels.2. Allowable EOOS conditions are listed in Section 9.0.3. Based on 0.500 second turbinetrip time delay with OLMCPR > 1.27.Page 10 of 57 Exelon Nuclear -Nuclear Fuels DOC ID: COLR Clinton 1 Rev. 5 CLIC13 Core Operating Limits Report Non-Proprietary Information Submitted in Accordance with 10 CFR 2.390...Table 4-3 Flow Dependent MCPR Limits MCPR(F)1 (Reference 3)Core Flow MCPR(F) MCPR(F)(% rated) GE14C -GEI41 0.000 1.8819 1.9519 25.000 1.70 1.77 84.100 I' 1.27 93.721 -1.27 109.000 1.27 .1.27.Table 4-4 Single Loop Operation (SLO) Flow Dependent MCPR Limits MCPR(F)2 (Reference. | .GE141 Fuel GE141 Fuel C Option B .Option A; Option B Option A Combination All exposures All-exposures All exposures All exposures Base Case DLO 1.291 1:35 1.36 1.42 Base Case SLO 2' 1.32 1.38 1.39 1.45 1TBVOOS DLO 1.291 1.35 1.36 1.42 1TBVOOS SLO 2 1.32 1.38 1.39 1.45 TBSOOS DLO 1.30 1.40 1.37 1.47 TBSOOS SLO 2 1.33 1.43 1.40 1.50 Notes for Table 4-1: 1. Analyzed DLO Option B OLMCPR is 1.27 per Reference 3, value is adjusted to obtain an OPRM amplitude setpoint of 1.10.2. SLO Option A(B) OLMCPR is the DLO Option A(B) OLMCPR plus 0.03.Page,9of 57 Exelon Nuclear -Nuclear Fuels CLIC13 Core Operating Limits Report Non-Proprietary Information Submitted in Accordance with 10 CFR 2.390 DOC ID:. COLR Clinton 1. Rev. 5..Table 4-2 Power Dependent MCPR Limits" MCPR(P) and Multipliers K(P)1 2 (References 3 and 7)EQOS Core Flow -Core Thermal Power (%)Combito (% of 0 121.6 <S33.3 >33.3 1<43 >431 <70 >70 100 Rated) _ MCPR(P) .I.. -.. .. K(P)3 Base Case DLO <_50 2.20 2.20 1.97 1.351 1.347 1.313 1.212 1.15 1.00 GE14C > 50 2.46 2.46 2.17 Base Case SLO <_50 2.23 2.23 2.00 1:351 1.347 1.313 1.212 1.15 1.00 GE14C > 50 2.49 2.49 2.20 Base Case DLO < 50 2.27 2.27 2.04 1.351 1.347 1.313 1.212 1.15 1.00 GE141 > 50 2.53 2.53 2.24 Base Case SLO < 50 2.30 2.30 2.07 1.351... 1.347 .1.313 1.212 1.15 1.00 GE141 > 50 2.56 2.56 2.271 Notes for Table 4-2: 1. Values are interpolated between relevant power levels.2. Allowable EOOS conditions are listed in Section 9.0.3. Based on 0.500 second turbinetrip time delay with OLMCPR > 1.27.Page 10 of 57 Exelon Nuclear -Nuclear Fuels DOC ID: COLR Clinton 1 Rev. 5 CLIC13 Core Operating Limits Report Non-Proprietary Information Submitted in Accordance with 10 CFR 2.390...Table 4-3 Flow Dependent MCPR Limits MCPR(F)1 (Reference 3)Core Flow MCPR(F) MCPR(F)(% rated) GE14C -GEI41 0.000 1.8819 1.9519 25.000 1.70 1.77 84.100 I' 1.27 93.721 -1.27 109.000 1.27 .1.27.Table 4-4 Single Loop Operation (SLO) Flow Dependent MCPR Limits MCPR(F)2 (Reference. | ||
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S0.00 0.442 25.00 0.612 30.00 0.646..82.18 1.00 109.00 1.00 1 Linear interpolation should be used for points not listed in Appendix A..2 Linear interpolation should be used for points not listed in Table 5-3.Linear interpolation should be used for points not listed in Table 5-4.Page 14 of 57 Exelon Nuclear -Nuclear Fuels CLIC13 Core Operating Limits Report Non-Proprietary Information Submitted in Accordance with 10 CFR 2.390 DOC ID: COLR Clinton 1 Rev. 5 Table 5-5 LHGR Single Loop Opetafion (SLO) Reduction Factor (Reference 3)Fuel,- LHGR Type SLO Type .Multiplier hAIl Fuel Typesi .0-.76 11 Table 5-6 Power Dependent LHGR Multiplier LHGRFAC(P) 1 (Loss of 'FULL' Feedwater Heating)(References 3, 8, 9, and 10)E s Core Thermal Power (% Rated)combination Core Flow, 0 21.6 < 33.3 > 33.3 100_ __LHGRFAC(P) | S0.00 0.442 25.00 0.612 30.00 0.646..82.18 1.00 109.00 1.00 1 Linear interpolation should be used for points not listed in Appendix A..2 Linear interpolation should be used for points not listed in Table 5-3.Linear interpolation should be used for points not listed in Table 5-4.Page 14 of 57 Exelon Nuclear -Nuclear Fuels CLIC13 Core Operating Limits Report Non-Proprietary Information Submitted in Accordance with 10 CFR 2.390 DOC ID: COLR Clinton 1 Rev. 5 Table 5-5 LHGR Single Loop Opetafion (SLO) Reduction Factor (Reference 3)Fuel,- LHGR Type SLO Type .Multiplier hAIl Fuel Typesi .0-.76 11 Table 5-6 Power Dependent LHGR Multiplier LHGRFAC(P) 1 (Loss of 'FULL' Feedwater Heating)(References 3, 8, 9, and 10)E s Core Thermal Power (% Rated)combination Core Flow, 0 21.6 < 33.3 > 33.3 100_ __LHGRFAC(P) | ||
Base Case DLO <50 0.627 0.627 0.682.> ;fn I r n r, r. n rQA4 0.682 0.99 Base Case SLO'Tabld 5-7 Flow Dependent LHGR Multiplier LHGRFAC(F) 2 (Loss of 'FULL' Feedwater Heating)(References 3, 8. 9, and 10)Core Flow LHGRFAC(F) | Base Case DLO <50 0.627 0.627 0.682.> ;fn I r n r, r. n rQA4 0.682 0.99 Base Case SLO'Tabld 5-7 Flow Dependent LHGR Multiplier LHGRFAC(F) 2 (Loss of 'FULL' Feedwater Heating)(References 3, 8. 9, and 10)Core Flow LHGRFAC(F) | ||
(% rated) L F 0.00 0.437!25.00 0.605 30.00 0.639 82.18 0.99 109.00 0.99 Linear interpolation should be used for points not listed in Table 5-6.2 Linear interpolation should be used for points not listed in Table 5-7.Page:1-' of 57 Exelon Nuclear -Nuclear Fuels CLI C13 Core Operating Limits Report Non-Proprietary Information Submitted in Accordance with 10 CFR 2.390 DOC ID: COLR Clinton I Rev. 5 Table 5-8 Flow Dependent LHGR Multiplier LHGRFAC(F) 1 -1TBVO.OS or TBSOOS..(References 3 and 6)Core Flow T L ..FA(F (% rated) LHGRFAC(F) 0.00 0.14000 25.00 0.36500 40.00 0.50000 50.00 0.63000 98.30 1.00000 109.00 1.00000 Table 5-9 Flow Dependent LHGR Multiplier LHGRFAC(F) 2 -ITBVOOS orTBSOOS (Loss of 'FULL' Feedwater Heating)(References 3, 6, 8, 9, and 1.0)Core Flow 1 (% rated) L R J 0 0.13860 25.00: 0.36135 40.00 0.49500 50.00 0.62370 98.30 0.99000 109.00 0.99000 1 Linear interpolation should be used for points not listed in Table 5-8.2 Linear interpolation should be used for points not listed in Table 5-9.Page 16.of 57 Exelon Nuclear -Nuclear Fuels CLC103 Core Operating Limits Report Non-Proprietary Information Submitted in Accordance with 10 CFR 2.390 DOC ID: COLR Clinton 1 Rev. 5 6.0 Reaicto0iProtection System (RPS) lnst'ruimentation | (% rated) L F 0.00 0.437!25.00 0.605 30.00 0.639 82.18 0.99 109.00 0.99 Linear interpolation should be used for points not listed in Table 5-6.2 Linear interpolation should be used for points not listed in Table 5-7.Page:1-' of 57 Exelon Nuclear -Nuclear Fuels CLI C13 Core Operating Limits Report Non-Proprietary Information Submitted in Accordance with 10 CFR 2.390 DOC ID: COLR Clinton I Rev. 5 Table 5-8 Flow Dependent LHGR Multiplier LHGRFAC(F) 1 -1TBVO.OS or TBSOOS..(References 3 and 6)Core Flow T L ..FA(F (% rated) LHGRFAC(F) 0.00 0.14000 25.00 0.36500 40.00 0.50000 50.00 0.63000 98.30 1.00000 109.00 1.00000 Table 5-9 Flow Dependent LHGR Multiplier LHGRFAC(F) 2 -ITBVOOS orTBSOOS (Loss of 'FULL' Feedwater Heating)(References 3, 6, 8, 9, and 1.0)Core Flow 1 (% rated) L R J 0 0.13860 25.00: 0.36135 40.00 0.49500 50.00 0.62370 98.30 0.99000 109.00 0.99000 1 Linear interpolation should be used for points not listed in Table 5-8.2 Linear interpolation should be used for points not listed in Table 5-9.Page 16.of 57 Exelon Nuclear -Nuclear Fuels CLC103 Core Operating Limits Report Non-Proprietary Information Submitted in Accordance with 10 CFR 2.390 DOC ID: COLR Clinton 1 Rev. 5 6.0 Reaicto0iProtection System (RPS) lnst'ruimentation 6.1 Technical Specification | ||
Specification | |||
==Reference:== | ==Reference:== | ||
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== Description:== | == Description:== | ||
The Average Power Range Monitor (APRM) simulated thermal power time constant, shall be between 5.4 seconds and 6.6 seconds (Reference 12).7.0 Turbine Bypass System Reactor Power Limitation | The Average Power Range Monitor (APRM) simulated thermal power time constant, shall be between 5.4 seconds and 6.6 seconds (Reference 12).7.0 Turbine Bypass System Reactor Power Limitation 7.1 Technical Specification | ||
Specification | |||
==Reference:== | ==Reference:== | ||
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== Description:== | == Description:== | ||
Table 7-1 provides the maximum allowable reactor power with 1 TBVOOS or TBSOOS as specified in Technical Specification.. | Table 7-1 provides the maximum allowable reactor power with 1 TBVOOS or TBSOOS as specified in Technical Specification.. | ||
3.7.6 action statement A. 1.Table 7-1 Reactor Power Limitation.- | |||
statement A. 1.Table 7-1 Reactor Power Limitation.- | |||
ITBVOOS or TBSOOS:(Reference 6)Maximum Reactor Power Turbine Bypass System Status (% rated)1TBVOOS 100.0 TBSOOS 97.0 Page 17 of 57 Exelon Nuclear -Nuclear Fuels CLIC13 Core Operating Limits Report Non-Proprietary Information Submitted in Accordance with 10 CFR 2.390 DOC ID: COLR Clinton I Rev. 5 8.0 Stability Protection Setpoints The'Clinton I Cycle 13 oPRM Period Based Detection Algorithm (PBDA) Trip Setpoints for the OPRM System for use in Technical Specification 3.3.1.3 are found in Table 8-1. These values are based on the cycle specific analysis documented in Reference 3.Any change to the OLMCPR value and/or ARTS-based power dependent MCPR limits should be evaluated for potential impact on the OPRM PBDA Trip Setpoints. | ITBVOOS or TBSOOS:(Reference 6)Maximum Reactor Power Turbine Bypass System Status (% rated)1TBVOOS 100.0 TBSOOS 97.0 Page 17 of 57 Exelon Nuclear -Nuclear Fuels CLIC13 Core Operating Limits Report Non-Proprietary Information Submitted in Accordance with 10 CFR 2.390 DOC ID: COLR Clinton I Rev. 5 8.0 Stability Protection Setpoints The'Clinton I Cycle 13 oPRM Period Based Detection Algorithm (PBDA) Trip Setpoints for the OPRM System for use in Technical Specification 3.3.1.3 are found in Table 8-1. These values are based on the cycle specific analysis documented in Reference 3.Any change to the OLMCPR value and/or ARTS-based power dependent MCPR limits should be evaluated for potential impact on the OPRM PBDA Trip Setpoints. | ||
Table 8-1 OPRM PBDA Trip Setpoints (Reference 3)S PBDA Trip Amp'.litude .Corresponding Maximum Confirmation Count Trip Setting 1.10 13 , Page 18 of 57 Exelon Nuclear -Nuclear Fuels CLLC13 Core Operating Limits Report Non-Proprietary Information Submitted in Accordance with 10 CFR 2.390 DOC ID: COLR Clinton 1 Rev. 5 9.0 Modes of Operation The Allowed Modes of Operation with combinations of Equipment Out-of-Service (EOOS) are as described belowin Table 9-1: Tablera 9-1 Modes of Operation (Reference 3)Operating Region EOOS Options Standard MELLLA ICF FFWTR 1 Coastdown Base Case DLO, Option A Yes Yes Yes Yes Yes Base Case SLO 1 , Option A Y No N Yes No No No Yes Base Case DLO, Option B.Yes .. ..Yes ...Yes... Yes Yes Base Case SLO 1 , Option B Yes No No No Yes Base Case DLO, Option A, Yes Yes Yes Yes Yes 1TBVOOS Base Case SLO 1 , Option A, Yes No No No Yes 1TBVOOS Base Case DLO, Option B, Yes Yes Yes Yes Yes 1TBVOOS Base Case SLO 1 , Option B, Yes No No No Yes 1TBVOOS Base Case DLO, Option A, Yes Yes Yes Yes Yes TBSOOS Base Case SLO 1 , Option A, Yes No No No Yes TBSOOS Base Case DLO, Option B, Yes Yes Yes Yes Yes TBSOOS Base Case SLO 1 , Option B, Yes No No No Yes TBSOOS Notes: 1. Concurrent operation with SLO and Loss of'FULL' Feedwater Heating (+/-10*F of design NORMAL temperature) or FFWTR has not been evaluated and thus is not a valid operating mode. (References 3, 8, 9 and 10)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 document: 1. "General Electric Standard Application for Reactor Fuel", NEDE-2401 1-P-A-16, October 2007 and U.S. Supplement NEDE-2401 1-P-A-16-US, October 2007.'Page 19 of 57 Exelon Nuclear -Nuclear Fuels DOC ID: COLR Clinton 1 Rev. 5 CLI C13 Core Operating Limits Report Non-Proprietary Information Submitted in Accordance with 10 CFR 2.390 2. "BWR Owners' Group Reactor Stability Detect and Suppress Solutions Licensing Basis Methodology and Reload Applications", NEDO-32465, August 1996 11.0 References | Table 8-1 OPRM PBDA Trip Setpoints (Reference 3)S PBDA Trip Amp'.litude .Corresponding Maximum Confirmation Count Trip Setting 1.10 13 , Page 18 of 57 Exelon Nuclear -Nuclear Fuels CLLC13 Core Operating Limits Report Non-Proprietary Information Submitted in Accordance with 10 CFR 2.390 DOC ID: COLR Clinton 1 Rev. 5 9.0 Modes of Operation The Allowed Modes of Operation with combinations of Equipment Out-of-Service (EOOS) are as described belowin Table 9-1: Tablera 9-1 Modes of Operation (Reference 3)Operating Region EOOS Options Standard MELLLA ICF FFWTR 1 Coastdown Base Case DLO, Option A Yes Yes Yes Yes Yes Base Case SLO 1 , Option A Y No N Yes No No No Yes Base Case DLO, Option B.Yes .. ..Yes ...Yes... Yes Yes Base Case SLO 1 , Option B Yes No No No Yes Base Case DLO, Option A, Yes Yes Yes Yes Yes 1TBVOOS Base Case SLO 1 , Option A, Yes No No No Yes 1TBVOOS Base Case DLO, Option B, Yes Yes Yes Yes Yes 1TBVOOS Base Case SLO 1 , Option B, Yes No No No Yes 1TBVOOS Base Case DLO, Option A, Yes Yes Yes Yes Yes TBSOOS Base Case SLO 1 , Option A, Yes No No No Yes TBSOOS Base Case DLO, Option B, Yes Yes Yes Yes Yes TBSOOS Base Case SLO 1 , Option B, Yes No No No Yes TBSOOS Notes: 1. Concurrent operation with SLO and Loss of'FULL' Feedwater Heating (+/-10*F of design NORMAL temperature) or FFWTR has not been evaluated and thus is not a valid operating mode. (References 3, 8, 9 and 10)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 document: 1. "General Electric Standard Application for Reactor Fuel", NEDE-2401 1-P-A-16, October 2007 and U.S. Supplement NEDE-2401 1-P-A-16-US, October 2007.'Page 19 of 57 Exelon Nuclear -Nuclear Fuels DOC ID: COLR Clinton 1 Rev. 5 CLI C13 Core Operating Limits Report Non-Proprietary Information Submitted in Accordance with 10 CFR 2.390 2. "BWR Owners' Group Reactor Stability Detect and Suppress Solutions Licensing Basis Methodology and Reload Applications", NEDO-32465, August 1996 11.0 References | ||
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: 3. Global Nuclear Fuel Document, 0000-0099-4244-SRLR Revision 0, "Supplemental Reload Licensing Report for Clinton Power Station Unit 1 Reload 12 Cycle 13", December 2009.4. Global Nuclear Fuel Document, 0000-0099-4244-FBIR-P Revision 0, "Fuel Bundle Information Report for Clinton Power Station Unit 1 Reload 12 Cycle 13", December 2009.5. General Electric Document, GE-NE-0000-0000-7456-01P, "Option B Scram Times For Clinton Power Station", February 2002 6. GE Hitachi Nuclear Energy (GEH) Document, 0000-0086-4634-R2-P, "Clinton Power Station One Bypass Out of Service or Turbine Bypass System Out of Service Analysis -Final", Revision 1, July 2010 7. General Electric Document, GE-NE-0000-0042-4570-RO, "Clinton Offrated Analyses Below the PLU Power Level," September 2005.8. Exelon Design Analysis, GENE-0000-0030-8309, "Engineering Report Clinton Assessment of Feedwater Riser Flow Deviation," Rev. 0, June 14, 2005.9. Exelon Engineering Change, EC 355034 RO, "Feedwater Riser Flow Deviation Assessment", August 4, 2005 10. Exelon Engineering Change, EC 354185 RO, "Uncertainty in Feedwater Temperature for Two Loop and Single Loop Operation", April 5, 2005 11. Exelon Transmittal of Design Information, TODI NF0900164 Revision 1, "Clinton Unit 1 Cycle 13 FRED Form Revision 1 (APPROVED)", October 30, 2009 12. Exelon Transmittal of Design Information, TODI ES0900019 Revision 0, "Clinton Unit 1 Cycle 13 Resolved OPL-3 Values", October 15, 2009.Page 20,of 57 Exelon Nuclear -Nuclear Fuels CLIC13 Core Operating Limits Report Non-Proprietary Information Submitted in Accordance with 10 CFR 2.390 DOC ID: COLR Clinton I Rev. 5 Appendix A Page 21 of 57 CLLC13 Core Operating Limits Report Non-Proprietary Information submitted in DOC ID: COLR Clinton 1 Rev. 5 Accordance with 10 CFR 2.390 Appendix A Global Nuclear Fuel -Americas AFFIDAVIT I, Anthony P. Reese, state as follows: (1) I am Manager, Reload Design & Analysis, Global Nuclear Fuel-Americas,,: | : 3. Global Nuclear Fuel Document, 0000-0099-4244-SRLR Revision 0, "Supplemental Reload Licensing Report for Clinton Power Station Unit 1 Reload 12 Cycle 13", December 2009.4. Global Nuclear Fuel Document, 0000-0099-4244-FBIR-P Revision 0, "Fuel Bundle Information Report for Clinton Power Station Unit 1 Reload 12 Cycle 13", December 2009.5. General Electric Document, GE-NE-0000-0000-7456-01P, "Option B Scram Times For Clinton Power Station", February 2002 6. GE Hitachi Nuclear Energy (GEH) Document, 0000-0086-4634-R2-P, "Clinton Power Station One Bypass Out of Service or Turbine Bypass System Out of Service Analysis -Final", Revision 1, July 2010 7. General Electric Document, GE-NE-0000-0042-4570-RO, "Clinton Offrated Analyses Below the PLU Power Level," September 2005.8. Exelon Design Analysis, GENE-0000-0030-8309, "Engineering Report Clinton Assessment of Feedwater Riser Flow Deviation," Rev. 0, June 14, 2005.9. Exelon Engineering Change, EC 355034 RO, "Feedwater Riser Flow Deviation Assessment", August 4, 2005 10. Exelon Engineering Change, EC 354185 RO, "Uncertainty in Feedwater Temperature for Two Loop and Single Loop Operation", April 5, 2005 11. Exelon Transmittal of Design Information, TODI NF0900164 Revision 1, "Clinton Unit 1 Cycle 13 FRED Form Revision 1 (APPROVED)", October 30, 2009 12. Exelon Transmittal of Design Information, TODI ES0900019 Revision 0, "Clinton Unit 1 Cycle 13 Resolved OPL-3 Values", October 15, 2009.Page 20,of 57 Exelon Nuclear -Nuclear Fuels CLIC13 Core Operating Limits Report Non-Proprietary Information Submitted in Accordance with 10 CFR 2.390 DOC ID: COLR Clinton I Rev. 5 Appendix A Page 21 of 57 CLLC13 Core Operating Limits Report Non-Proprietary Information submitted in DOC ID: COLR Clinton 1 Rev. 5 Accordance with 10 CFR 2.390 Appendix A Global Nuclear Fuel -Americas AFFIDAVIT I, Anthony P. Reese, state as follows: (1) I am Manager, Reload Design & 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. | 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 the GNF proprietary report, 0000-0099-4244-FBIR-P, Fuel Bundle Information Report for Clinton Power Station Unit 1 Reload 12 Cycle 13, Class 111, (GNF-A Proprietary Information), , Revision 0,.. dated December 2009. The GNF proprietary information in 0000-0099-4244-FBIR-P is identified by a dotted underline inside double square brackets. | .(2) The information sought to be withheld' is contained in the GNF proprietary report, 0000-0099-4244-FBIR-P, Fuel Bundle Information Report for Clinton Power Station Unit 1 Reload 12 Cycle 13, Class 111, (GNF-A Proprietary Information), , Revision 0,.. dated December 2009. The GNF proprietary information in 0000-0099-4244-FBIR-P is identified by a dotted underline inside double square brackets. | ||
[[Thjissentence is an exam pk.. .3..]] A"[[" marking at the beginning of a table, figure, or paragraph closed with a "]]" marking at the end of the table, figure or paragraph: | [[Thjissentence is an exam pk.. .3..]] A"[[" marking at the beginning of a table, figure, or paragraph closed with a "]]" marking at the end of the table, figure or paragraph: | ||
is used to, indicate that the entire content between the double brackets is proprietary. | is used to, indicate that the entire content between the double brackets is proprietary. | ||
'In each case, the superscript notation , refers to Paragraph (3) of this affidavit, which provides the basis for the proprietary determination. | 'In each case, the superscript notation , 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), andthe 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. | (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), andthe 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 Proiect v.Nuclear Regulatory Commission, 975F2d871 (DC Cir. 1992), and Public Citizen Health Research Group v. FDA, 704F2d1280(DC Cir. 1983).(4) Some examples of categories | Mass Energy Proiect v.Nuclear Regulatory Commission, 975F2d871 (DC Cir. 1992), and Public Citizen Health Research Group v. FDA, 704F2d1280(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;. | :of information which fit into the definition' of proprietary information are: a. Information that discloses a process;. | ||
method, or apparatus,- | method, or apparatus,- | ||
Line 157: | Line 147: | ||
3240 120T- I 50-T6-3240 (GE I 4C)GE14I-PIOSCOB405-13GZ-3243 120T- 150-T6-3243 (GE 141)GE 14-P 1 OSNAB418-15GZ-120T- 150-T6-3242 (GE I4C)GE I 4-P] OSNAB422-13GZ-120T- 150-T6-3239 (GE I4C)GE I 4-PI OSNAB418-15GZ-120T-150-T6-3241 (GEI4C)GE14-P1OSNAB420-15GZ-120T- 150-T6-2870 (GE I4C)GE 14-P 1 OSNAB419-14GZ-120T-150-T6-2871 (GEI4C) 2 15 Maximum lattice k6,tfor the most reactive* | 3240 120T- I 50-T6-3240 (GE I 4C)GE14I-PIOSCOB405-13GZ-3243 120T- 150-T6-3243 (GE 141)GE 14-P 1 OSNAB418-15GZ-120T- 150-T6-3242 (GE I4C)GE I 4-P] OSNAB422-13GZ-120T- 150-T6-3239 (GE I4C)GE I 4-PI OSNAB418-15GZ-120T-150-T6-3241 (GEI4C)GE14-P1OSNAB420-15GZ-120T- 150-T6-2870 (GE I4C)GE 14-P 1 OSNAB419-14GZ-120T-150-T6-2871 (GEI4C) 2 15 Maximum lattice k6,tfor the most reactive* | ||
uncontrolled state plus a [[1] adder for uncertainties. | uncontrolled state plus a [[1] adder for uncertainties. | ||
Page 19 COLR Page 43 of 57 CLIC13 Core Operating Limits Report Non-Proprietary Information submitted in Accordance with 10 CFR 2.390 Clinton Non-Proprietary Information Reload 12 Class I DOC ID: COLR Clinton 1 Rev. 5 Appendix A 0000-0099-4244-FBIR-NP Rev.ision 0 4F]]Figure B-1 Enrichment and Gadolinium DiStribution for EDB No. 3028 Fuel Bundle GE14-PiOSNAB417-15GZ-120T-150-T6-3028 (GE14C)Page 20 COLR Page 44 of 57 CLIC13 Core Operating Limits Report Non-Proprietary Information submitted in Accordance with 10 CFR 2.390 DOC ID: COLR Clinton 1 Rev. 5 Appendix A 0000-0099-4244-FBIR-NP Revision 0 Clinton Reload 12 Non-Proprietary Information Class I[[1],Figure B-2. Enrichment apnd Gadolinium Distribution for EDB No. 3027''Fuel Bundle GE14-P1OSNAB418-14GZ-120T-150-T6-3027 (GE14C)Page 21 COLR Page 45 of 57 CL1C13 Core Operating Limits Repo Non-Proprietary Information submitte Accordance with 10 CFR 2.390 Clinton Reload 12 DOC ID: COLR Clinton 1 Rev. 5 Appendix A 0000-0099-4244-FBIR-NP Revision 0 Non-Proprietary Information Class I[[Figure B-3 Enrichment and Gadolinium Distribution for'EDB No. 3029 Fuel Bundle GE14-PiOSNAB418-15GZ-120T-150-T6-3029 (GE14C)Page 22 COLR Page 46 of 57 CL1C13 Core Operating Limits Repo Non-Proprietary Information submitte Accordance with 10 CFR 2.390 Clinton Reload 12 DOC ID: COLR Clinton 1 Rev. 5 Appendix A 0000-0099-4244-FBIR-NP Revision 0 Non-Proprietary Information Class I Figure B-4 Enrichment and Gadolinium Distribution for EDB No. 3031"Fuiel Bundle.GE14-P1OSNAB422-13GZ-120T-150-T6-3031 (GE14C)Page 23 COLR Page 47 of 57 CLLC13 Core Operating Limits Repc Non-Proprietary Information submittE Accordance with 10 CFR 2.390 Clinton Reload 12 DOC ID: COLR Clinton 1 Rev. 5 Appendix A 0000-0099-4244-F BIR-NP Revision 0 Non-Proprietary Information Class I]]Figure B-5 Enrichment.and Gadolinium | Page 19 COLR Page 43 of 57 CLIC13 Core Operating Limits Report Non-Proprietary Information submitted in Accordance with 10 CFR 2.390 Clinton Non-Proprietary Information Reload 12 Class I DOC ID: COLR Clinton 1 Rev. 5 Appendix A 0000-0099-4244-FBIR-NP Rev.ision 0 4F]]Figure B-1 Enrichment and Gadolinium DiStribution for EDB No. 3028 Fuel Bundle GE14-PiOSNAB417-15GZ-120T-150-T6-3028 (GE14C)Page 20 COLR Page 44 of 57 CLIC13 Core Operating Limits Report Non-Proprietary Information submitted in Accordance with 10 CFR 2.390 DOC ID: COLR Clinton 1 Rev. 5 Appendix A 0000-0099-4244-FBIR-NP Revision 0 Clinton Reload 12 Non-Proprietary Information Class I[[1],Figure B-2. Enrichment apnd Gadolinium Distribution for EDB No. 3027''Fuel Bundle GE14-P1OSNAB418-14GZ-120T-150-T6-3027 (GE14C)Page 21 COLR Page 45 of 57 CL1C13 Core Operating Limits Repo Non-Proprietary Information submitte Accordance with 10 CFR 2.390 Clinton Reload 12 DOC ID: COLR Clinton 1 Rev. 5 Appendix A 0000-0099-4244-FBIR-NP Revision 0 Non-Proprietary Information Class I[[Figure B-3 Enrichment and Gadolinium Distribution for'EDB No. 3029 Fuel Bundle GE14-PiOSNAB418-15GZ-120T-150-T6-3029 (GE14C)Page 22 COLR Page 46 of 57 CL1C13 Core Operating Limits Repo Non-Proprietary Information submitte Accordance with 10 CFR 2.390 Clinton Reload 12 DOC ID: COLR Clinton 1 Rev. 5 Appendix A 0000-0099-4244-FBIR-NP Revision 0 Non-Proprietary Information Class I Figure B-4 Enrichment and Gadolinium Distribution for EDB No. 3031"Fuiel Bundle.GE14-P1OSNAB422-13GZ-120T-150-T6-3031 (GE14C)Page 23 COLR Page 47 of 57 CLLC13 Core Operating Limits Repc Non-Proprietary Information submittE Accordance with 10 CFR 2.390 Clinton Reload 12 DOC ID: COLR Clinton 1 Rev. 5 Appendix A 0000-0099-4244-F BIR-NP Revision 0 Non-Proprietary Information Class I]]Figure B-5 Enrichment.and Gadolinium | ||
:Distribution for EDB No. 3025 Fuel Bundle GE14-P1OSNAB422-15GZr12OT-150-T6-3025 | :Distribution for EDB No. 3025 Fuel Bundle GE14-P1OSNAB422-15GZr12OT-150-T6-3025 | ||
:(GE14C)Page 24 COLR Page 48 of 57 CL1C13 Core Operating Limits Repc Non-Proprietary Information submittE Accordance with 10 CFR 2.390 Clinton Reload 12 DOC ID:'COLR Clinton 1 Rev. 5 Appendix A 0000-0099-4244-FBIR-NP Revision 0 Non-Proprietary Information Class I'Figure B-6 Enrichment'and Gadolinium Distribution for EDB No. 3030 Fuel Bundle GEI4-P1OSNAB419-14GZ-ý120T-150-T6-3030 (GE14C)Page 25 COLR Page 49 of 57 CL1C13 Core Operating Limits Repc Non-Proprietary Information submitte Accordance with 10 CFR 2.390 Clinton Reload 12 DOC ID: COLR Clinton 1 Rev. 5 Appendix A 0000-0099-4244-FBIR-NP Revision 0 Non-Proprietary Information Class I Figure B-7 Enrichment and Gadolinium Distribution for EDB No. 3026 , Fuel Bundle GE14-P1OSNAB413-16GZ-120T-150-T6-3026,(GE14C) | :(GE14C)Page 24 COLR Page 48 of 57 CL1C13 Core Operating Limits Repc Non-Proprietary Information submittE Accordance with 10 CFR 2.390 Clinton Reload 12 DOC ID:'COLR Clinton 1 Rev. 5 Appendix A 0000-0099-4244-FBIR-NP Revision 0 Non-Proprietary Information Class I'Figure B-6 Enrichment'and Gadolinium Distribution for EDB No. 3030 Fuel Bundle GEI4-P1OSNAB419-14GZ-ý120T-150-T6-3030 (GE14C)Page 25 COLR Page 49 of 57 CL1C13 Core Operating Limits Repc Non-Proprietary Information submitte Accordance with 10 CFR 2.390 Clinton Reload 12 DOC ID: COLR Clinton 1 Rev. 5 Appendix A 0000-0099-4244-FBIR-NP Revision 0 Non-Proprietary Information Class I Figure B-7 Enrichment and Gadolinium Distribution for EDB No. 3026 , Fuel Bundle GE14-P1OSNAB413-16GZ-120T-150-T6-3026,(GE14C) | ||
Page 26 COLR Page 50 of 57 CLIC13 Core Operating Limits Repo Non-Proprietary Information submitte Accordance with 10 CFR 2.390 Clinton Reload 12 DOC ID: COLR Clinton 1 Rev. 5 Appendix A 0000-0099-4244-FBIR-NP Revision 0 Non-Proprietary Information Class I Figure B-8 Enrichment and Gadolinium Distribution for EDB No. 3240., Fuel Bundle GE14-P1OSNAB418-15GZ-120T-150-T6-3240 (GE14C)Page 27 COLR Page 51 of 57 CLIC13 Core Operating Limits Report Non-Proprietary Information submitted in Accordance with 10 CFR 2.390 Clinton Nor Relnad 12 DOC ID: COLR Clinton 1 Rev. 5 Appendix A 0000-0099-4244-FBIR-NP Revision 0 9 i-Proprietary Information Class I Figure B-9 Enrichment and Gadolin'ium Distribution for EDB No. 3243*Fuel Bundle GE141-P1OSCOB405-13GZ-120T-150-T6-3243 (GE14I)Page 28 COLR Page 52 of .57 CL1C13 Core Operating Limits Report Non-Proprietary Information submitted in Accordance with 10 CFR 2.390 Clinton Non-Proprietary Information Reload 12 Class I DOC ID: COLR Clinton 1 Rev. 5 Appendix A 0000-0099-4244-FBIR-NP Revision 0 1]Figure B-10 Enrichment axid- Gadolinium. | Page 26 COLR Page 50 of 57 CLIC13 Core Operating Limits Repo Non-Proprietary Information submitte Accordance with 10 CFR 2.390 Clinton Reload 12 DOC ID: COLR Clinton 1 Rev. 5 Appendix A 0000-0099-4244-FBIR-NP Revision 0 Non-Proprietary Information Class I Figure B-8 Enrichment and Gadolinium Distribution for EDB No. 3240., Fuel Bundle GE14-P1OSNAB418-15GZ-120T-150-T6-3240 (GE14C)Page 27 COLR Page 51 of 57 CLIC13 Core Operating Limits Report Non-Proprietary Information submitted in Accordance with 10 CFR 2.390 Clinton Nor Relnad 12 DOC ID: COLR Clinton 1 Rev. 5 Appendix A 0000-0099-4244-FBIR-NP Revision 0 9 i-Proprietary Information Class I Figure B-9 Enrichment and Gadolin'ium Distribution for EDB No. 3243*Fuel Bundle GE141-P1OSCOB405-13GZ-120T-150-T6-3243 (GE14I)Page 28 COLR Page 52 of .57 CL1C13 Core Operating Limits Report Non-Proprietary Information submitted in Accordance with 10 CFR 2.390 Clinton Non-Proprietary Information Reload 12 Class I DOC ID: COLR Clinton 1 Rev. 5 Appendix A 0000-0099-4244-FBIR-NP Revision 0 1]Figure B-10 Enrichment axid- Gadolinium. | ||
Distribution for EDB No. 3242 Fuel Bundle GE14-P1OSNAB418-15GZ-120T-150-T6-3242 (GE14C)Page 29 COLR Page 53 of 57 CL1C13 Core Operating Limits Repo Non-Proprietary Information submitte Accordance with 10 CFR 2.390 Clinton Reload 12 DOC ID: COLR Clinton 1 Rev. 5 Appendix A 0000-0099-4244-FBIR-NP Revision 0 S Non-Proprietary Information Class I 1]Figure B-11 Enrichment and Gadolinium-Di~tribution for EDBNo. 3239 Fuel Bundle GE14-PlOSNAB422-l3GZ-120T-150-T6-3239 (GE14C)Page 30 COLR Page 54 of 57 CLI C1 3 Core Operating Limits Report Non-Proprietary Information submitted in Accordance with 10 CFR 2.390 Clinton -Non-Proprietary Information Reload 12- Class I DOC ID: COLR Clinton 1 Rev. 5 Appendix A 0000-0099-4244-FBIR-NP Revision 0 1]Figure B-12 Enrichment and.Gadolinium Distribution for EDB No. 3241 a. Fuel Bundle GE14-P1OSNAB418-15GZ-120T-150-T6-3241 (GE14C)Page 31 COLR Page 55 of 57 CL1C13 Core Operating Limits Repc Non-Proprietary Information submitte Accordance with 10 CFR 2.390 Clinton Reload 12 DOC ID: COLR Clinton 1 Rev. 5 Appendix A 0000-0099-4244-FBIR-NP Revision 0-p Non-Proprietary Information Class I.Figure B-13. Enrichment.and GadoliniumDistribution for EDBNo. 2870 Fuel Bundle GE14-P1OSNAB420-15GZ-120T-150-T6-2870 (GE14C)Page 32 COLR Page 56.of 57 CL1C13 Core Operating Limits Report S., ">' Non-Proprietary Information submitted in Accordance with 10 CFR 2.390 Clinton Non-Proprietary Information Reload 12 Class I DOC ID: COLR Clinton 1 Rev. 5 Appendix A 0000-0099-4244-FBIR-NP Revision 0 Figure B-14 Enrichnient and Gadolinium'Distribution for EDB No. 2871 Fuel Bundle (GE14C)Page 33 COLR Page 57 of 57}} | Distribution for EDB No. 3242 Fuel Bundle GE14-P1OSNAB418-15GZ-120T-150-T6-3242 (GE14C)Page 29 COLR Page 53 of 57 CL1C13 Core Operating Limits Repo Non-Proprietary Information submitte Accordance with 10 CFR 2.390 Clinton Reload 12 DOC ID: COLR Clinton 1 Rev. 5 Appendix A 0000-0099-4244-FBIR-NP Revision 0 S Non-Proprietary Information Class I 1]Figure B-11 Enrichment and Gadolinium-Di~tribution for EDBNo. 3239 Fuel Bundle GE14-PlOSNAB422-l3GZ-120T-150-T6-3239 (GE14C)Page 30 COLR Page 54 of 57 CLI C1 3 Core Operating Limits Report Non-Proprietary Information submitted in Accordance with 10 CFR 2.390 Clinton -Non-Proprietary Information Reload 12- Class I DOC ID: COLR Clinton 1 Rev. 5 Appendix A 0000-0099-4244-FBIR-NP Revision 0 1]Figure B-12 Enrichment and.Gadolinium Distribution for EDB No. 3241 a. Fuel Bundle GE14-P1OSNAB418-15GZ-120T-150-T6-3241 (GE14C)Page 31 COLR Page 55 of 57 CL1C13 Core Operating Limits Repc Non-Proprietary Information submitte Accordance with 10 CFR 2.390 Clinton Reload 12 DOC ID: COLR Clinton 1 Rev. 5 Appendix A 0000-0099-4244-FBIR-NP Revision 0-p Non-Proprietary Information Class I.Figure B-13. Enrichment.and GadoliniumDistribution for EDBNo. 2870 Fuel Bundle GE14-P1OSNAB420-15GZ-120T-150-T6-2870 (GE14C)Page 32 COLR Page 56.of 57 CL1C13 Core Operating Limits Report S., ">' Non-Proprietary Information submitted in Accordance with 10 CFR 2.390 Clinton Non-Proprietary Information Reload 12 Class I DOC ID: COLR Clinton 1 Rev. 5 Appendix A 0000-0099-4244-FBIR-NP Revision 0 Figure B-14 Enrichnient and Gadolinium'Distribution for EDB No. 2871 Fuel Bundle (GE14C)Page 33 COLR Page 57 of 57}} |
Revision as of 09:43, 30 April 2019
ML11265A046 | |
Person / Time | |
---|---|
Site: | Clinton |
Issue date: | 09/16/2011 |
From: | Davis B W, Becknell G W Exelon Nuclear, Exelon Generation Co |
To: | Document Control Desk, Office of Nuclear Reactor Regulation |
References | |
U-604038 | |
Download: ML11265A046 (60) | |
Text
{{#Wiki_filter:S.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. ExelknNuclear Clinton Power Station 8401 Power Road Clinton, IL 61727 U-604038 1 OCFR50.36 September 16, 2011 U. S. Nuclear Regulatory Commission Attention: Document Control Desk Washington, D. C. 20555-0001 Clinton Power Station, Unit 1 Facility Operating License No. NPF-62 NRC Docket No. 50-461
Subject:
Submittal of the Core Operating Limits Report for Clinton Power Station, Unit 1, Cycle 13 Revision In accordance with Technical Specification 5.6.5, "Core Operating Limits Report (COLR)," Item d., Exelon Generation Company (EGC), LLC is submitting a mid-cycle revision of the COLR for Clinton Power Station, Unit 1. This revision is associated with the implementation of License Amendment 195 approved by the NRC on August 17, 2011, associated with TS 3.7.6, Main Turbine Bypass. Attachment 1 contains a proprietary version of the COLR that is requested to be withheld from public disclosure in accordance with 10CFR2.390(a)(4). This submittal is subdivided as follows: 1. Attachment 1 provides a proprietary version of the COLR. Appendix A of this attachment contains an affidavit that attests to the proprietary nature of the information contained in the document.2. Attachment 2 contains a non-proprietary version of the COLR documented in Attachment 1.Should you have any questions concerning this report, please contact me at (217) 937-2800.Respectfully, Brian W. Davis Regulatory Assurance Manager Clinton Power Station Attachment 1 Contains Proprietary Information Withhold From Public Disclosure Under 10 CFR 2.390(a)(4). When Separated From Attachment 1, Cover Letter Is Decontrolled. liar I Attachment 1 Contains Proprietary Information Withhold From Public Disclosure Under 10 CFR 2.2390(A)(4). When Separated From Attachment 1, Cover Letter Is Decontrolled. U.S. Nuclear Regulatory Commission U-604038 Page 2 of 2 JLP/blf Attachments:
- 1. Core Operating Limits Report for Clinton Power Station Unit 1, Cycle 13 (Proprietary Version)2. Core Operating Limits Report for Clinton Power Station Unit 1, Cycle 13 (Non-Proprietary Version)cc: NRC Regional Administrator, Region III NRC Senior Resident Inspector
-Clinton Power Station Attachment 1 Contains Proprietary Information Withhold From Public Disclosure Under 10 CFR 2.390(a)(4). When Separated From Attachment 1, Cover Letter Is Decontrolled. Attachment 1 Contains Proprietary Information Withhold From Public Disclosure Under 10 CFR 2.390(a)(4). When Separated From Attachment 1, Cover Letter Is Decontrolled. U.S. Nuclear Regulatory Commission U-604038 ATTACHMENT 2 Core Operating Limits Report for Clinton Power Station Unit 1, Cycle 13 (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. Exelon Nuclear -Nuclear Fuels CLIC13 Core Operating Limits Report Nan-PrculpWm Infatmaion Submald in Accordance with 10 CFR 2.390 DOC I1: COLR Clinton I Rev. 5 I I CORE OPERATING LIMITS REPORT FOR CLINTON POWER STATION UNIT I CYCLE 13 J.Prepared By" Reviewed By: Reviewed By: Reviewed By: Gary W. Becknell RE Reviewer"f eviewer Date: 9/1/10 Date: 9,hi(b Date: 1P,-//0 Date: A)Date: Date:iLIi Indepjn~d~t Reviewer Approved By: _____ ____'James J. Tusar Station Qualified Reviewer By:-Page I of 57 Exelon Nuclear -Nuclear Fuels DOC ID: COLR Clinton I Rev. 5 CLIC13 Core Operating Limits Report Proprietary Information Submitted in Accordance with 10 CFR 2.390 Table of Contents Page 1.0 Terms and Definitions 4 2.0 General Information 5 3.0 MAPLHGR Limits 6 4.0 MCPR Limits 7 5.0 Linear Heat Generation Rate Limits 13 6.0 Reactor Protection System (RPS) Instrumentation 17 7.0 Turbine Bypass System Reactor Power Limitation 17 8.0 Stability Protection Setpoints 18 9.0 Modes of Operation 19 10.0 Methodology 19 11.0 References 20 Appendix A 21 Page 2 of 57 Exelon Nuclear -Nuclear Fuels DOC ID: COLR Clinton I Rev. 5 CLLC13 Core Operating Limits Report Non-Proprietary Information Submitted in Accordance with 10 CFR 2.390 List of Tables Page Table 3-1 MAPLHGR for All Fuel Types 6 Table 3-2 MAPLHGR Single Loop Operation (SLO) Multiplier 6 Table 4-1 Operating Limit Minimum Critical Power Ratio 9 Table 4-2 Power Dependent MCPR Limits MCPR(P) and Multipliers K(P) 10 Table 4-3 Flow Dependent MCPR Limits MCPR(F) 11 Table 4-4 Single Loop Operation (SLO) Flow Dependent MCPR Limits MCPR(F) 11 Table 4-5 Flow Dependent MCPR Limits MCPR(F) -1TBVOOS or TBSOOS 12 Table 4-6 Single Loop Operation (SLO) Flow Dependent MCPR Limits MCPR(F) -1TBVOOS or TBSOOS 12 Table 5-1 Linear Heat Generation Rate Limits for U0 2 Rods 13 Table 5-2 Linear Heat Generation Rate Limits for Gad Rods 14 Table 5-3 Power Dependent LHGR Multiplier LHGRFAC(P) 14 Table 5-4 Flow Dependent LHGR Multiplier LHGRFAC(F) 14 Table 5-5 LHGR Single Loop Operation (SLO) Reduction Factor 15 Table 5-6 Power Dependent LHGR Multiplier LHGRFAC(P)(Loss of 'FULL' Feedwater Heating) 15 Table 5-7 Flow Dependent LHGR Multiplier LHGRFAC(F)(Loss of 'FULL' Feedwater Heating) 15 Table 5-8 Flow Dependent LHGR Multiplier LHGRFAC(F) -1TBVOOS or TBSOOS 16 Table 5-9 Flow Dependent LHGR Multiplier LHGRFAC(F) -1TBVOOS or TBSOOS (Loss of 'FULL' Feedwater Heating) 16 Table 7-1 Reactor Power Limitation -1TBVOOS or TBSOOS 17 Table 8-1 OPRM PBDA Trip Setpoints 18 Table 9-1 Modes of Operation 19 Page 3 of 57 Exelon Nuclear -Nuclear Fuels CLIC13 Core Operating Limits Report Non-Proprietary Information Submitted in Accordance with 10 CFR 2.390 1.0 Terms and Definitions DOCID: COLR Clinton I Rev. 5 I Base Case .A case analyzed with two (2) Safety-Relief Valves Out-of-Service (oos), one (1)ADS 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 adjustments and multipliers LHGRFAC(P) LHGR thermal limit power dependent adjustments and, multipliers MAPLHGR Maximum Average Planar Linear Heat Generation Rate MCPR Minimum Critical Power Ratio MCPR(P) MCPR thermal limit power dependent adjustments and multipliers MCPR(F) MCPR thermal limit flow dependent adjustments and multipliers OLMCPR Operating Limit Minimum Critical Power Ratio OPRM Oscillation Power Range Monitor SLMCPR Safety Limit Minimum Critical Power Ratio SLO Single Reactor Recirculation Loop Operation TBSOOS Turbine Bypass System Out of Service 1TBVOOS One Turbine Bypass Valve Out of Service Page.4 of 57 Exelon Nuclear -Nuclear Fuels DOC ID: COLR Clinton I Rev. 5 CLL C13 Core Operating Limits Report Non-Proprietary Information Submitted in Accordance with 10 CFR 2.390 2.0 General Information This repoit is prepared in accordance with Technical Specificationr 5.6.5 of Reference
- 1. P0wer 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 Reference 2 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
-.,* Feedwater Heater Out of Service (FWHOOS) up to 50°F feedwater temperature reduction at any time during the cycle prior to cycle extension. The Clinton Unit 1 Cycle 13 COLR was revised mid-cycle (Revision
- 5) under EC 380905 to support operation with 1TBVOOS or TBSOOS. The changes are indicated by revision bars in the right hand margin. It should be noted that the MCPR(F) values-for the 0.000% core flow point in Tables 4-5 and 4-6 are different than those specified in References 3 and 6. The difference is due to References 3 and 6 truncating/rounding the value to two (2) significant digits. The Values presented in Tables 4-5 and 4-6 are in agreement with the databank thermal limit set and are conservative.
Page"s'of 57 Exelon Nuclear -Nuclear Fuels CLIC13 Core Operating Limits Report Non-Proprietary Information Submitted in Accordance with 10 CFR 2.390 DOC ID: COLR Clinton I Rev. 5 3.0 MAPLHGR Limits 3.1 Technical Specification
Reference:
Sections 3.2.1 and 3.4.1.3.2
Description:
Table 3-1 is used to determine the maximum average planar linear heat generation rate (MAPLHGR)limit for each fuel type. Limits listed in Table 3-1 are for dual reactor recirculation loop operation (DLO).For single reactor recirculation loop operation (SLO), the MAPLHGR limits given in Table 3-1 must be multiplied by a SLO MAPLHGR multiplier provided in Table 3-2. The SLO MAPLHGR multiplier for all fuel is 0.76 (Reference 3).:Table 3-1 MAPLHGR for All Fuel Types'(Reference 3)Avg. Planar Exposure MAPLHGR Limit (GWdlST) " (kWlft)0.00 12.82 14.51 1.2.82 19.13 12.82 57.61 8.00 63.50 5.00 Table 3-2., MAPLHGR Single Loop Operation (SLO) Multiplier:.(Reference 3)Fuel MAPLHGR Type SLO Multiplier All Fuel Types 0.76 Linear interpolation should be used for points not listed in Table 3-1.....Page 6 of 57 Exelon Nuclear -Nuclear Fuels DOC ID: COLR Clinton I Rev. 5 CL1C13 Core Operating Limits Report Non-Proprietary Information Submitted in Accordance with 10 CFR 2.390 4.0 MCPR Limits 4.1 Technical Specification
Reference:
Sections 3.2.2, 3.4.1, and 3.7.6 4.2
Description:
The various MCPR limits are described below.4.2.1 Manual Flow Control MCPR Limits The Operating Limit MCPR (OLMCPR) is determined from either section 4:2.1.1 or 4.2.1.2, whichever is greater at any given power and flow condition' 4.2.1.1 Power-Dependent MCPR For operation less than or equal to 33.3% core thermal power, the MCPR(P) as a function of core thermal power is shown in Table 4-2. For .operation at greater than 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.The Base Case (DLO and SLO) MCPR(P) and K(P) given in Table 4-2 are also applicable to the corresponding condition with 1TBVOOS or TBSOOS (References 3 and 6).4.2.1.2 Flow-Dependent MCPR Tables 4-3 through 4-6 give the MCPR(F) as a function of flow based on the applicable plant condition. The limits for dual.loop operationarelisted in Table 4-3. The limits for single loop operation are listed in Table 4-4. The limits for dual loop operation with 1TBVOOS or TBSOOS are listed in Table 4-5. The limits for single loop operation with 1TBVOOS or TBSOQS arelisted in Table 4-6'. The MCPR(F) determined from these tables is the flow dependent OLMCPR.4.2.2 Automatic Flow Control MCPR Limits Automatic Flow Control MCPR Limits are not provided.,Page.7 of 57 Exelon Nuclear -.Nuclear Fuels DOC ID: COLR Clinton I Rev. 5 CLLC13 Core Operating Limits Report Non-Proprietary Information Submitted in Accordance with 10 CFR 2.390 4.2.3 Option A and Option B Option A and Option B refer to use of scram speeds for establishing MCPR operating limits.Option A scram speed is the BWR/6 Technical Specification scram speed. The Technical Specification scram speeds must be met to utilize the Option A MCPR limits. Reload analyses. performed by GNF for.Cycle,13 Option A.MCPR limits utilized a 20% core average insertion time of 0.516 seconds (Reference 12).To utilize the MCPR limits for the Option B scram speed, the cycle average scram insertion time for 20% insertion must satisfy equation 2 in Reference 5.Section
- 4. If the cycle average scram insertion time does not meet the Option B criteria, the appropriate MCPR value may be determined from a linear interpolation between the Option A and B limits as specified by equation 4 in Reference 5 Section 4.4.2.4 Recirculation Flow Control Valve Settings Cycle 13 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 11).Page 8 of 57 Exelon Nuclear- Nuclear Fuels CLL C13 Core Operating Limits Report Non-Proprietary Information Submitted in Accordance with 10 CFR 2.390 DOC ID: COLR Clinton 1 Rev. 5 Table 4-1 Operating Limit Minimum Critical Power Ratio" '(Reference 3)EOS. GE14C Fuel GE14CFuel
.GE141 Fuel GE141 Fuel C Option B .Option A; Option B Option A Combination All exposures All-exposures All exposures All exposures Base Case DLO 1.291 1:35 1.36 1.42 Base Case SLO 2' 1.32 1.38 1.39 1.45 1TBVOOS DLO 1.291 1.35 1.36 1.42 1TBVOOS SLO 2 1.32 1.38 1.39 1.45 TBSOOS DLO 1.30 1.40 1.37 1.47 TBSOOS SLO 2 1.33 1.43 1.40 1.50 Notes for Table 4-1: 1. Analyzed DLO Option B OLMCPR is 1.27 per Reference 3, value is adjusted to obtain an OPRM amplitude setpoint of 1.10.2. SLO Option A(B) OLMCPR is the DLO Option A(B) OLMCPR plus 0.03.Page,9of 57 Exelon Nuclear -Nuclear Fuels CLIC13 Core Operating Limits Report Non-Proprietary Information Submitted in Accordance with 10 CFR 2.390 DOC ID:. COLR Clinton 1. Rev. 5..Table 4-2 Power Dependent MCPR Limits" MCPR(P) and Multipliers K(P)1 2 (References 3 and 7)EQOS Core Flow -Core Thermal Power (%)Combito (% of 0 121.6 <S33.3 >33.3 1<43 >431 <70 >70 100 Rated) _ MCPR(P) .I.. -.. .. K(P)3 Base Case DLO <_50 2.20 2.20 1.97 1.351 1.347 1.313 1.212 1.15 1.00 GE14C > 50 2.46 2.46 2.17 Base Case SLO <_50 2.23 2.23 2.00 1:351 1.347 1.313 1.212 1.15 1.00 GE14C > 50 2.49 2.49 2.20 Base Case DLO < 50 2.27 2.27 2.04 1.351 1.347 1.313 1.212 1.15 1.00 GE141 > 50 2.53 2.53 2.24 Base Case SLO < 50 2.30 2.30 2.07 1.351... 1.347 .1.313 1.212 1.15 1.00 GE141 > 50 2.56 2.56 2.271 Notes for Table 4-2: 1. Values are interpolated between relevant power levels.2. Allowable EOOS conditions are listed in Section 9.0.3. Based on 0.500 second turbinetrip time delay with OLMCPR > 1.27.Page 10 of 57 Exelon Nuclear -Nuclear Fuels DOC ID: COLR Clinton 1 Rev. 5 CLIC13 Core Operating Limits Report Non-Proprietary Information Submitted in Accordance with 10 CFR 2.390...Table 4-3 Flow Dependent MCPR Limits MCPR(F)1 (Reference 3)Core Flow MCPR(F) MCPR(F)(% rated) GE14C -GEI41 0.000 1.8819 1.9519 25.000 1.70 1.77 84.100 I' 1.27 93.721 -1.27 109.000 1.27 .1.27.Table 4-4 Single Loop Operation (SLO) Flow Dependent MCPR Limits MCPR(F)2 (Reference. 3)Core Flow MCPR(F) 1 MCPR(F)(% rated)_ GE14C GE141 0.000 1.9119 1.9819 25.000 1.73 1.80 84.100 1.30-93.721 , 1.30 109.000 1.30 1.30 1 Linear interpolation should be used for points not listed in Table 4-3.2 Linear interpolation should be used for points not listed in Table 4-4.Page 1 of 57 Exelon Nuclear -Nuclear Fuels CLIC13 Core Operating Limits Report Non-Proprietary Information Submitted in Accordance with 10 CFR 2.390 DOC ID: COLR Clinton 1 Rev. 5 Table 4-5 Flow Dependent MCPR Limits MCPR(F)1 -1TBVOOS or TBSOOS (References 3 and 6)Core Flow MCPR(F) MCPR(F)(% rated) GE14C GE141 0.000 2.0435 2.1135 25.000 '1.85 1.92 99.954 1.27 109.000 1.27 1.27 Table 4-6 Single Loop Operation (SLO) Flow Dependent MCPR Limits MCPR(F)2 -1TBVOOS or TBSOOS (References 3 and 6).Core Flow MCPR(F) MCPR(F)(% rated) GEI4C .GE141 0.000 2.0735 2.1435 25.000 1.88" 1.95 99.954 1.30 109.000 .1.30 1.30 Linear interpolation should be used for points not listed in Table 4-5..2 Linear interpolation should be used for points not listed in Table 4-6..i,.,Page. 12 of 57 Exelon Nuclear -Nuclear Fuels CLIC13 Core Operating Limits Report Non-Proprietary Information Submitted in Accordance with 10 CFR 2.390 DOC ID: COLR Clinton 1 Rev. 5 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 Table 5-4. The SLO multiplication factor can be found in Table 5-5. Tables 5-1 and 5-2 are the LHGR limit as a function of peak pellet exposure.-The Gadolinia fuel rod limits referienced in Table 5-2 are the most limiting Gadolinia fuel'rods. The most limiting values are provided here as a convenience and do not imply that all the Gadolinia fuel rods must satisfy the listed values..... .For Loss of 'FULL' Feedwater Heating (+/-10 'F of design NORMAL temperature), LHGRFAC(P) is determined from Table-5-6 and LHGRFAC(F) is determined from Table 5-7. Concurrent operation with SLO and reduced feedwater heating'has not been evaluated and thus is not a valid operating mode. (References 3, 7, 8, 9 and 10)The Base Case (DLO and SLO) LHGRFAC(P) given in Table 5-3 or 5-6 are also applicable to the corresponding condition with 1TBVOOS or TBSOOS depending on feedwater heating status (References 3 and 6).With 1TBVOOS or TBSOOS, the LHGRFAC(F) is determined from Table 5-8 or 5-9 depending on feedwater heating status.Table 5-1 Linear Heat Generation Rate Limits for U0 2 Rods 1 (Reference 4)Fuel Type LHGR Limit GE14C See Appendix A GE141 See Appendix A Linear interpolation should be used for points not listed in Appendix A.Page 13 of 57 Exelon Nuclear -Nuclear Fuels CLIC13 Core Operating Limits Report Non-Proprietary Information Submitted in Accordance with 10 CFR 2.390 DOC ID: COLR Clinton I Rev. 5...._ .: Table 5-2 Linear Heat Generation Rate Limits for Gad Rods 1 (Reference 4)Fuel.Type LHGR Limit GE14C See Appendix A GE141 See Appendix A Table 5-3 Power Dependent LHGR Multiplier LHGRFAC(P) 2 (Reference 3)1 Core Core Thermal Power (% Rated)EOOS Combination 0 21.6 < 33.3 >33.3 100__________ o "LHGRFAC(P) Base Case DLO < 50 0.634 0.634 0.689: 0.689 1.000> 50 0.572 0.572 0.600"< 50 0.634 0.634 0.689, 0 Base Case SLO > " 05 0572 0.600 .689 Table 5-4 Flow Dependent LHGR Multiplier LHGRFAC(F) 3 (Reference 3)Core Flow I (% rated)_ LHGRFAC(F) S0.00 0.442 25.00 0.612 30.00 0.646..82.18 1.00 109.00 1.00 1 Linear interpolation should be used for points not listed in Appendix A..2 Linear interpolation should be used for points not listed in Table 5-3.Linear interpolation should be used for points not listed in Table 5-4.Page 14 of 57 Exelon Nuclear -Nuclear Fuels CLIC13 Core Operating Limits Report Non-Proprietary Information Submitted in Accordance with 10 CFR 2.390 DOC ID: COLR Clinton 1 Rev. 5 Table 5-5 LHGR Single Loop Opetafion (SLO) Reduction Factor (Reference 3)Fuel,- LHGR Type SLO Type .Multiplier hAIl Fuel Typesi .0-.76 11 Table 5-6 Power Dependent LHGR Multiplier LHGRFAC(P) 1 (Loss of 'FULL' Feedwater Heating)(References 3, 8, 9, and 10)E s Core Thermal Power (% Rated)combination Core Flow, 0 21.6 < 33.3 > 33.3 100_ __LHGRFAC(P) Base Case DLO <50 0.627 0.627 0.682.> ;fn I r n r, r. n rQA4 0.682 0.99 Base Case SLO'Tabld 5-7 Flow Dependent LHGR Multiplier LHGRFAC(F) 2 (Loss of 'FULL' Feedwater Heating)(References 3, 8. 9, and 10)Core Flow LHGRFAC(F) (% rated) L F 0.00 0.437!25.00 0.605 30.00 0.639 82.18 0.99 109.00 0.99 Linear interpolation should be used for points not listed in Table 5-6.2 Linear interpolation should be used for points not listed in Table 5-7.Page:1-' of 57 Exelon Nuclear -Nuclear Fuels CLI C13 Core Operating Limits Report Non-Proprietary Information Submitted in Accordance with 10 CFR 2.390 DOC ID: COLR Clinton I Rev. 5 Table 5-8 Flow Dependent LHGR Multiplier LHGRFAC(F) 1 -1TBVO.OS or TBSOOS..(References 3 and 6)Core Flow T L ..FA(F (% rated) LHGRFAC(F) 0.00 0.14000 25.00 0.36500 40.00 0.50000 50.00 0.63000 98.30 1.00000 109.00 1.00000 Table 5-9 Flow Dependent LHGR Multiplier LHGRFAC(F) 2 -ITBVOOS orTBSOOS (Loss of 'FULL' Feedwater Heating)(References 3, 6, 8, 9, and 1.0)Core Flow 1 (% rated) L R J 0 0.13860 25.00: 0.36135 40.00 0.49500 50.00 0.62370 98.30 0.99000 109.00 0.99000 1 Linear interpolation should be used for points not listed in Table 5-8.2 Linear interpolation should be used for points not listed in Table 5-9.Page 16.of 57 Exelon Nuclear -Nuclear Fuels CLC103 Core Operating Limits Report Non-Proprietary Information Submitted in Accordance with 10 CFR 2.390 DOC ID: COLR Clinton 1 Rev. 5 6.0 Reaicto0iProtection System (RPS) lnst'ruimentation 6.1 Technical Specification
Reference:
Section 3.3.1.1 6.2
Description:
The Average Power Range Monitor (APRM) simulated thermal power time constant, shall be between 5.4 seconds and 6.6 seconds (Reference 12).7.0 Turbine Bypass System Reactor Power Limitation 7.1 Technical Specification
Reference:
Section 3.7.6 7.2
Description:
Table 7-1 provides the maximum allowable reactor power with 1 TBVOOS or TBSOOS as specified in Technical Specification.. 3.7.6 action statement A. 1.Table 7-1 Reactor Power Limitation.- ITBVOOS or TBSOOS:(Reference 6)Maximum Reactor Power Turbine Bypass System Status (% rated)1TBVOOS 100.0 TBSOOS 97.0 Page 17 of 57 Exelon Nuclear -Nuclear Fuels CLIC13 Core Operating Limits Report Non-Proprietary Information Submitted in Accordance with 10 CFR 2.390 DOC ID: COLR Clinton I Rev. 5 8.0 Stability Protection Setpoints The'Clinton I Cycle 13 oPRM Period Based Detection Algorithm (PBDA) Trip Setpoints for the OPRM System for use in Technical Specification 3.3.1.3 are found in Table 8-1. These values are based on the cycle specific analysis documented in Reference 3.Any change to the OLMCPR value and/or ARTS-based power dependent MCPR limits should be evaluated for potential impact on the OPRM PBDA Trip Setpoints. Table 8-1 OPRM PBDA Trip Setpoints (Reference 3)S PBDA Trip Amp'.litude .Corresponding Maximum Confirmation Count Trip Setting 1.10 13 , Page 18 of 57 Exelon Nuclear -Nuclear Fuels CLLC13 Core Operating Limits Report Non-Proprietary Information Submitted in Accordance with 10 CFR 2.390 DOC ID: COLR Clinton 1 Rev. 5 9.0 Modes of Operation The Allowed Modes of Operation with combinations of Equipment Out-of-Service (EOOS) are as described belowin Table 9-1: Tablera 9-1 Modes of Operation (Reference 3)Operating Region EOOS Options Standard MELLLA ICF FFWTR 1 Coastdown Base Case DLO, Option A Yes Yes Yes Yes Yes Base Case SLO 1 , Option A Y No N Yes No No No Yes Base Case DLO, Option B.Yes .. ..Yes ...Yes... Yes Yes Base Case SLO 1 , Option B Yes No No No Yes Base Case DLO, Option A, Yes Yes Yes Yes Yes 1TBVOOS Base Case SLO 1 , Option A, Yes No No No Yes 1TBVOOS Base Case DLO, Option B, Yes Yes Yes Yes Yes 1TBVOOS Base Case SLO 1 , Option B, Yes No No No Yes 1TBVOOS Base Case DLO, Option A, Yes Yes Yes Yes Yes TBSOOS Base Case SLO 1 , Option A, Yes No No No Yes TBSOOS Base Case DLO, Option B, Yes Yes Yes Yes Yes TBSOOS Base Case SLO 1 , Option B, Yes No No No Yes TBSOOS Notes: 1. Concurrent operation with SLO and Loss of'FULL' Feedwater Heating (+/-10*F of design NORMAL temperature) or FFWTR has not been evaluated and thus is not a valid operating mode. (References 3, 8, 9 and 10)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 document: 1. "General Electric Standard Application for Reactor Fuel", NEDE-2401 1-P-A-16, October 2007 and U.S. Supplement NEDE-2401 1-P-A-16-US, October 2007.'Page 19 of 57 Exelon Nuclear -Nuclear Fuels DOC ID: COLR Clinton 1 Rev. 5 CLI C13 Core Operating Limits Report Non-Proprietary Information Submitted in Accordance with 10 CFR 2.390 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. Global Nuclear Fuel Document, "General Electric Standard Application for Reactor Fuel", NEDE-24011-P-A-16, October 2007 and U.S. Supplement NEDE-24011-P-A-16-US, October2007.
- 3. Global Nuclear Fuel Document, 0000-0099-4244-SRLR Revision 0, "Supplemental Reload Licensing Report for Clinton Power Station Unit 1 Reload 12 Cycle 13", December 2009.4. Global Nuclear Fuel Document, 0000-0099-4244-FBIR-P Revision 0, "Fuel Bundle Information Report for Clinton Power Station Unit 1 Reload 12 Cycle 13", December 2009.5. General Electric Document, GE-NE-0000-0000-7456-01P, "Option B Scram Times For Clinton Power Station", February 2002 6. GE Hitachi Nuclear Energy (GEH) Document, 0000-0086-4634-R2-P, "Clinton Power Station One Bypass Out of Service or Turbine Bypass System Out of Service Analysis -Final", Revision 1, July 2010 7. General Electric Document, GE-NE-0000-0042-4570-RO, "Clinton Offrated Analyses Below the PLU Power Level," September 2005.8. Exelon Design Analysis, GENE-0000-0030-8309, "Engineering Report Clinton Assessment of Feedwater Riser Flow Deviation," Rev. 0, June 14, 2005.9. Exelon Engineering Change, EC 355034 RO, "Feedwater Riser Flow Deviation Assessment", August 4, 2005 10. Exelon Engineering Change, EC 354185 RO, "Uncertainty in Feedwater Temperature for Two Loop and Single Loop Operation", April 5, 2005 11. Exelon Transmittal of Design Information, TODI NF0900164 Revision 1, "Clinton Unit 1 Cycle 13 FRED Form Revision 1 (APPROVED)", October 30, 2009 12. Exelon Transmittal of Design Information, TODI ES0900019 Revision 0, "Clinton Unit 1 Cycle 13 Resolved OPL-3 Values", October 15, 2009.Page 20,of 57 Exelon Nuclear -Nuclear Fuels CLIC13 Core Operating Limits Report Non-Proprietary Information Submitted in Accordance with 10 CFR 2.390 DOC ID: COLR Clinton I Rev. 5 Appendix A Page 21 of 57 CLLC13 Core Operating Limits Report Non-Proprietary Information submitted in DOC ID: COLR Clinton 1 Rev. 5 Accordance with 10 CFR 2.390 Appendix A Global Nuclear Fuel -Americas AFFIDAVIT I, Anthony P. Reese, state as follows: (1) I am Manager, Reload Design & 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 the GNF proprietary report, 0000-0099-4244-FBIR-P, Fuel Bundle Information Report for Clinton Power Station Unit 1 Reload 12 Cycle 13, Class 111, (GNF-A Proprietary Information), , Revision 0,.. dated December 2009. The GNF proprietary information in 0000-0099-4244-FBIR-P is identified by a dotted underline inside double square brackets. Thjissentence is an exam pk.. .3.. A"" marking at the beginning of a table, figure, or paragraph closed with a "" marking at the end of the table, figure or paragraph: is used to, indicate that the entire content between the double brackets is proprietary. 'In each case, the superscript notation , 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), andthe 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 Proiect v.Nuclear Regulatory Commission, 975F2d871 (DC Cir. 1992), and Public Citizen Health Research Group v. FDA, 704F2d1280(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.
0000-0099-4244-FBIR-P Affidavit Page 1 of 3 COLR Page 22 of 57 v CLLC13 Core Operating Limits Report Non-Proprietary Information submitted in DOC ID: COLR Clinton 1 Rev. 5 Accordance with 10 CFR 2.390 Appendix A The information sought to be withheld -is considered to be proprietary 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. Disclosuresoutside GNF-A are limited to regulatory bodies, customers, and potential customers, and theiragents, 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 the methods used in these~analyses, .along with the testing, development and approval of the supporting methodology was achieved at a significant cost to GNF-A or its licensor. .... ....0000-0099-4244-FBIR-P Affidavit Page 2 of 3 COLR Page 23 of 57 CL1C13 Core Operating Limits Report Non-Proprietary Information submitted in DOC ID: COLR Clinton 1 Rev. 5 Accordance with 10 CFR 2.390 Appendix A (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.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 advantagewillbe 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 suclo 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. .; * -1 : 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 7 th day of December 2009., I, Manii-ger, Reload Design & Analysis Global Nuclear Fuel -Americas, LLC 0000-0099-4244-FBIR-P Affidavit Page 3 of 3 COLR Page 24 of 57 CL1C13 Core Operating Limits Report Non-Proprietary Information submitted in Accordance with 10 CFR 2.390 DOC ID: COLR Clinton 1 Rev. 5 Appendix A GNr Global Nuclear Fuel AJointVeinlure of GE, Toshiba. & Hitachi 0000-0099-4244-FBIR-NP Revision 0 Class I December 2009 Non-Proprietary Information Fuel Bundle Information Report for Clinton Power Station Unit 1 Reload 12 Cycle 13 Copyright 2009 Global Nuclear Fuels-Americas, LLC All Rights Reserved COLR Page 25 of 57 CLIC13 Core Operating Limits Report Non-Proprietary Information submitted in DOC ID: COLR Clinton 1 Rev. 5 Accordance with 10 CFR 2.390 Appendix A Clinton Non-Proprietary Information 0000-0099-4244-FBIR-NP Reload 12 Class I 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 0000-0099-4244-FBIR-P, 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 COLR Page 26 of 57 CL1C13 Core Operating Limits Report Non-Proprietary Information submitted in DOC ID: COLR Clinton 1 Rev. 5 Accordance with 10 CFR 2.390 Appendix A Clinton Non-Proprietary Information 0000-0099-4244-FBIR-NP Reload 12 Class I Revision 0 1. Introduction and Summary This report, which supplements the Supplemental Reload Licensing Report, contains thermal-mechanical linear heat generation rate (LHGR) limits for the GNF-A fuel designs to be loaded into Clinton Power Station Unit I for Cycle 13. These LHGR limits are obtained from thermal-mechanical considerations only. Approved GNF-A. calculation models documented in Reference 1 were used in performing this analysis.LHGR limits aý 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 tfiis appendix. These bundles have been approved for use under the*fuel licensi.ng acceptance criteria of Reference 1.Page 3 COLR Page 27 of 57 CL1C13 Core Operating Limits Repc Non-Proprietary Information submitte Accordance with 10 CFR 2.390 Clinton Reload 12 DOC ID: COLR Clinton 1 Rev. 5 Appendix A 0000-0099-4244-FBIR-NP Rev ision 0 Non-Proprietary Information Class I 2. References
- 1. General Electric Standard Application for Reactor Fuel, NEDE-240 I-P-A-i16, October 2007;and the U.S. Supplement., NEDE-2401 I-P-A-I6-US, October 2007.Page 4 COLR Page 28 of 57 CL1C13 Core Operating Limits Report Non-Proprietary Information submitted in Accordance with 10 CFR 2.390 Clinton Non-Proprietary Information.Reload 12 -Class I DOC ID: COLR Clinton 1 Rev. 5 Appendix A 0000-0099-4244-FBIR-NP Revision 0 Appendix A UO 2/Gd Thermal-Mechanical LHGR Limits Bundle Type: GEI4-PI0SNAB417-15GZ-.1 20T-1 50-T6-3028 (GEI4C)Bundle Number: 3028 Peak Pellet Exposure U0 2 LHGR Limit GWd/MT (GWd/ST) kW/ft 0.00 (0.00) 13.40 16.00 (14.51) 13.40 63.50 (57.61) 8.00 70.00 (63.50) 5.00 Peak Pellet Exposure Most Limiting Gadolinia LHGR Limit'GWd/MT (GWd/ST) kW/ft 0.00 (0.00) 11.76 13.31 (12.08) 11.76 59.76 (54.21) 7.02 66.12 (59.98) 4.39 Bounding gadolinia LHGR limit for all gadolinium concentrations occurring in this bundle design ( 8.0% Gd).Page 5 COR Page 29 of 57 CL1C13 Core Operating Limits Rep(Non-Proprietary Information submittf Accordance with 10 CFR 2.390 Clinton Reload 12 DOC ID: COLR Clinton 1 Rev. 5 Appendix A 0000-0099-4244-FBIR-NP Revision 0 Non-Proprietary Information Class I Class I Revision 0 UO 2/Gd..Therma!.Mechanical LHGR Limits Bundle Type: GE I4-P I 0SNAB418-14GZ-1 20T- 1 50-T6-3027 (GE I 4C)Bundle Number: 3027 Peak Pellet Exposure U0 2 LHGR Limit GWd/MT (GWd/ST) kW/ft 0.00(0.00) 13.40 16.00 (14.51) 13.40'63.50 (57.61) 8.00 70.00 (63.50) 5.00 Peak Pellet Exposure Most Limiting Gadolinia LHGR Limit 2 GWd/MT (GWd/ST) kW/ft.0.00 (0.00) 11.76 13.31 (12.08) 11.76 59.76 (54.21) .. 7.02*66.12 (59.98) 4.39 2 Bounding gadolinia LHGR limit for all gadolinium concentrations occurring in this bundle design.( 8.0% Gd).Page 6 COLR Page 30 of 57 CL1C13 Core Operating Limits Repc Non-Proprietary Information submitte Accordance with 10 CFR 2.390 Clinton Reload 12 DOC ID: COLR Clinton 1 Rev. 5 Appendix A 0000-0099-4244-FBIR-NP Revision 0 Non-Proprietary Information Class I UO 2 1Gd ThermaI-Mechanical LHGR Limits Bundle Type: GE14-PIOSNAB418I 15GZ-120T-150-T6-3029 (GEI4C)Bundle Number: 3029 Peak Pellet Exposure U0 2 LHGR Limit GWd/MT (GWd/ST) kW/ft 0.00 (0.00) 13.40 16.00(14.51) 13.40 63.50 (57.61) 8.00 70.00 (63.50) 5.00.Peak Pellet Exposure Most Limiting Gadolinia LHGR Limit 3 GWd/MT (GWd/ST) kW/ft 0.00 (0.00) 11.76 13.31 (12.08) 11.76 59.76 (54.21) 7.02 66.12 (59.98) 4.39 3 Bounding gadolinia LHGR limit for all gadolinium concentrations occurring in this bundle design ( 8.0% Gd).Page 7 COLR Page 31 of 57 CLLC13 Core Operating Limits Report Non-Proprietary Information submitted in Accordance with 10 CFR 2.390.Clinton Non-Proprietary Information Reload 12 Class I DOC ID: COLR Clinton 1 Rev. 5 Appendix A 0000-0099-4244-FBIR-NP Revision 0...UO 2/Gd. Thermal-Mechanical LHGR: Limits Bundle Type: GE] 4-P I OSNAB422-13GZ-1 20T- 150-T6-3031 (GE 14C)Bundle Number: 3031 Peak Pellet Exposure U0 2 LHGR Limit GWd/MT (GWd/ST) kW/ft 0.00 (0.00) 13.40 16.00 (14.51) 13.40 63.50 (57.61) 8.00 70.00 (63.50) .*5.00 Peak Pellet Exposure Most Limiting Gadolinia LHGR Limit 4 GWd/MT (GWd/ST) kW/ft 0.00 (0.00) .11.76 13.31 (12.08) 11.76 59.76 (54.21) 7.02 66.12 (59.98) '4.39 4 Bounding gadolinia LHGR limit for all gadolinium concentrations occurring in this bundle'design ( 8.0% Gd).Page 8 COLR Page 32 of 57 CL1C13 Core Operating Limits Repc Non-Proprietary Information submittE Accordance with 10 CFR 2.390 Clinton Reload 12 DOC ID- COLR Clinton 1 Rev. 5 Appendix A 0000-0099-4244-FBIR-NP Revision 0 Non-Proprietary Information Class I U0 2!Gd Thermal-Mechanical LHGR Limits Bundle Type: GE 14-P I OSNAB422-15GZ-I 20T- 1 50-T6-3025 (GE I 4C)Bundle Number: 3025 Peak Pellet Exposure U0 2 LHGR Limit GWd/MT (GWd/ST) kW/ft.0.00 (0.00) 13.40 16.00 (14.51) 13.40 63.50(57.61) 8.00 70.00 (63.50) 5.00 Peak Pellet Exposure Most Limiting Gadolinia LHGR Limit 5 GWd/MT (GWd/ST) kW/ft 0.00 (0.00) 11.76 13.31 (12.08) 11.76 59.76 (54.21) 7.02 66.12 (59.98) 4.39 Bounding gadolinia.LHGRlimit for all gadolinium concentrations occurring in this bundle design ( 8.0% Gd)..Page 9 COLR Page 33 of 57 CLLC13 Core Operating Limits Repc Non-Proprietary Information submittE Accordance with 10 CFR 2.390 Clinton Reload 12 DOC ID: COLR Clinton 1 Rev. 5 Appendix A 0000-0099-4244-FBIR-NP Revision 0 Non-Proprietary Information Class I U0 2/1d Thermal-Mechanical LHGR.Limits Bundle Type: GE 14-Pi 0SNAB419-14GZ-120T- 150-T6-3030 (GE 14C)Bundle Number: 3030 Peak Pellet Exposure U,0 2 LHGR Limit GWd/MT (GWd/ST) kW/ft 0.00(0.00) 13.40 16.00(14.51) 13.40 63.50 (57.61) 8.00 70.00,(63.50) 5.00 Peak Pellet Exposure Most.Limiting Gadolinia LHGR Limit 6 GWd/MT (GWd/ST) kW/ft 0.00 (0.00) ,l 1.76 13.31 (12.08) 11.76 59.76 (54.21) 7.02.66.12 (59.98) ..4.39 6 Bounding gadolinia LHGR limit for all gadolinium concentrations occurring in this bundle. design ( 8.0% Gd).Page 10 COLR Page 34 of 57 CL1C13 Core Operating Limits Report Non-Proprietary Information submitted in Accordance with 10 CFR 2.390 Clinton Nor Reload '12.DOC ID: COLR Clinton 1 Rev. 5 Appendix A 0000-0099-4244-FBIR-NP
.. Revision 0 i-Proprietary Information Class 1'Reload,12 Revision 0*UO 2 1Gd ThermaIMechanical LHGR Limits Bundle Type: GE 14-P 1 SNAB413-16GZ-1 20T- 150-T6-3026 (GEl 4C)Bundle Number: 3026 Peak' Pellet Exposure U0 2 LHGR Limit GWd/MT (GWd/ST) kW/ft:": 0.00(0.00) 13.40 16.00 (!4.51). 13.40 63.50 (57.61) 8.00 70.00 (63.50). 5.00'Peak Pellet Exposure Most Limiting Gadolinia LHGR Limit 7 GWd/MT (GWd/ST) kW/ft 0.00(0.00) 11.76 13.31 (12.08) 1 1.76 59.76 (54.21) 7.02 66.12 (59.98) .4.39 7 Bounding gadolinia LHGR limit for all gadolinium concentrations occurring in this bundle design ( 8.0% Gd).Page 11 COLR Page 35 of 57 CL1C13 Core Operating Limits Repc Non-Proprietary Information submittE Accordance with 10 CFR 2.390 Clinton Reload 12 DOC ID: COLR Clinton 1 Rev. 5 Appendix A 0000-0099-4244-FBIR-NP Revision 0 Non-Proprietary Information Class I Class I Revision 0 UO 2/Gd Thermal-Mechanical LHGR Limits Bundle Type: GE I4-P I OSNAB418-15GZ-I 20T- I 50-T6-3240 (GE I 4C)Bundle Number: 3240 Peak Pellet Exposure U0 2 LHGR Limit GWd/MT (GWd/ST) kW/ft 0.00(0.00) 13.40 16.00 (14.51) 13.40 63.50 (57.61) 8.00 70.00 (63.50) 5.00 Peak Pellet Exposure Most Limiting Gadolinia LHGR Limit 8.GWd/MT (GWd/ST) kW/ft 0.00(0.00) 11.76-13.31 (12.08) 11.76 59.76 (54.21) 7.02 66.12 (59.98) 4.39 8 Bounding gadolinia LHGR limit for all gadolinium concentrations occurring in this bundle :design:( 8.0% Gd).Page 12 COLR Page 36 of 57 CLLC13 Core Operating Limits Report Non-Proprietary Information submitted in Accordance with 10 CFR 2.390 Clinton Nor Reload 12 DOC ID: COLR Clinton 1 Rev. 5 Appendix A 0000-0099-4244-FBIR-NP Revisinn "0 i-Proprietary Information Class I'UO 2 IGd ThermaI-Mechandical, LHGR. Limits Bundle Type: GE I41-P I OSCOB405-1 3GZ-120T-I 50-T6-3243 (GE 141)Bundle Number: 3243 Peak Pellet Exposure U0 2 LHGR Limit GWd/MT (GWd/ST) kW/ft: l[[Peak Pellet Exposure Most Limiting Gadolinia LHGR Limit 9 GWd/MT (GWd/ST) kW/ft[II ..._________________________________ I]]9 Bounding gadolinia.LHGR limit for all gadolinium concentrations occurring in this bundle design [[Page 13 COLR Page 37 of 57 CL1C13 Core Operating Limits Repc Non-Proprietary Information submittE Accordance with 10 CFR 2.390 Clinton Reload 12 DOC ID: COLR Clinton 1 Rev. 5 Appendix A 0000-0099-4244-FBIR-NP Revision 0 Non-Proprietary Information Class I Reload 12 Revision 0 UO 2 Gd ThermaI-Meqchanical LHGR Limits Bundle Type: GE 14-PIOSNAB418-15GZ-120T- 150-T6-3242 (GE 14C)Bundle Number: 3242 Peak Pellet Exposure U0 2 LHGR Limit GWd/MT (GWd/ST) kW/ft, 0.00(0.00) 13.40 16.00(14.51) 13.40 63.50(57.61) 8.00 70.00 (63.50) 5.00 Peak Pellet Exposure Most Limiting Gadolinia LHGR Limit 'o GWd/MT (GWd/ST) kW/ft 0.00(0.00) .11.76 13.31 (12.08) .11.76 59.76 (54.21) 7.02 66.12 (59.98) 4.39'o Bounding gadolinia LHGR limit for all gadolinium concentrations occurring in this bundledesign (8.0% Gd),.Page 14 COLR Page 38 of 57 CL1C13 Core Operating Limits Report Non-Proprietary Information submitted in Accordance with 10 CFR 2.390 Clinton Nor Relnad._l 2 DOC ID: COLR Clinton 1 Rev. 5 Appendix A 0000-0099-4244-FBIR-NP Revision 0 i-Proprietary Information Class I UO 2/Gd Thermal-MechanicAl LHGR Limits Bundle Type: GEl 4-PIOSNAB422-I 3GZ-120T-150-T6-3239 (GEI4C)Bundle Number: 3239 Peak Pellet Exposure U0 2 LHGRLiirLiit GWd/MT (GWd/ST) kW/ft 0.00(0.00) 13.40 16.00 (14.51) 13.40 .63.50 (57.61) 8.00 70.00 (63.50) 5.00 Peak Pellet Exposure Most Limiting Gadollinia LHGR Limit" GWd/MT (GWd/ST) kW/ft 0.00 (0.00) 11.76 13.31 (12.08) 11.76 59.76 (54.21) .7.02 66.12 (59.98) 4.39 1Bounding gadolinia LHGR limit for all gadolinium concentrations occurring in this bundle design ( 8.0% Gd).Page 15 COLR Page 39 of 57 CL1C13 Core Operating Limits Repc Non-Proprietary Information submitt(Accordance with 10 CFR 2.390 Clinton Reload 12 DOC ID: COLR Clinton 1 Rev. 5 Appendix A 0000-0099-4244-FBIR-NP Revision 0 4, Non-Proprietary Information Class I UO 2 1Gd ThermaI-Mechanical LHGR ,Limits Bundle Type: GE14-PI OSNAB418-15GZ-120T-150-T6-3241 (GEl 4C)Bundle Number: 3241 Peak Pellet Exposure U0 2 LHGR Limit GWd/MT (GWd/ST) kW/ft: 0.00(0.00) 13.40 16.00 (14.51) 13.40 63.50 (57.61) 8.00 70.00-(63.50) 5.00 Peak Pellet Exposqre Most Limiting Gadolinia LHGR Limit GWd/MT (GWd/ST) kW/ft 0.00(0.00) 11.76 13.31 (12.08) 11.76 59.76 (54.21) 7.02-66.12 (59.98) .4.39 12 Bounding gadolinia LHGR limit for all gadolinium concentrations occurring in this bundle design ( 8.0% Gd).Page 16 COLR Page 40 of 57 CL1C13 Core Operating Limits Repo Non-Proprietary Information submitte Accordance with 10 CFR 2.390 Clinton Reload. 12 DOC ID: COLR Clinton 1 Rev. 5 Appendix A 0000-0099-4244-FBIR-NP Revision 0 Non-Proprietary Information Class I:.UO 2 1Gd Thermal-Mbchanical LHIGR Limits Bundle Type: GEl 4-P 1 OSNAB420-15GZ-I 20T- I 50-T6-2870 (GE I4C)Bundle Number: 2870 Peak Pellet Exposure U0 2 LHGR Limit GWd/MT (GWd/ST) kW/ft o'o0 (0.00) 13.40o 16.00(14.51) 13.40 63.50 (57.61) 8.00 70;00 (63.50) 5.00 Peak Pellet Exposure Most Limiting Gadolinia LHGR Limit 1 3 GWd/MT (GWd/ST) kW/ft 0.00(0.00) 11.76 13.31 (12.08) 11.76 59.76 (54.2 ). 7.02 66.12 (59.98) 4.3 9"'3 Boundinggadolinia LHGR limit for all gadolinium concentrations occurring in this bundle design ( 8.0% Gd).Page 17 COLR Page41I "of 57 CL1C13 Core Operating Limits Report Non-Proprietary Information submitted in Accordance with 10 CFR 2.390 Clinton Non-Proprietary Information Reload 12 Class I DOC ID: COLR Clinton 1 Rev. 5 Appendix A 0000-0099-4244-FBIR-NP Revision 0 UO 2 lGd Thermal-Mechanical LHGR Limits Bundle Type: GE 14-P I OSNAB419-14GZ-1 20T- 1 50-T6-2871 (GE 14C)Bundle Number: 2871 Peak Pellet Exposure: U02 LHGR Limit GWd/MT (GWd/ST) kW/ft 0.00 ( 0:00) 13.40 16.00 (14.51) 13.40 63.50 (57.6,1) 8.00 70.00 (63.50) 5.00 Peak Pellet Exposure Most Limiting Gadolinia LHGR Limit 1 4 GWd/MT (GWd/ST) kW/ft 0.00 (0.00) 11.76 13.31 (12.08) 11.76 59.76 (54.21) 7.02 66.12 (.59.98) -4.39 -14 Bounding gadolinia LHGR limit for all gadoliniumconcentrations occurring in this bundle design ( 8.0% Gd).Page 18 COLR Page 42 of 57 CLLC13 Core Operating Limits Report Non-Proprietary Information submitted in Accordance with 10 CFR 2.390 Clinton Non-Proprietary Information
- Reload. 12. Class I DOC ID: COLR Clinton 1 Rev. 5 Appendix A 0000-0099-4244-FBIR-NP Revision 0 Appendix B: Fuel Bundle Information Table B-1 Bundle Specific Information Weight Weight Max Exposure Fuel Bundle Enrichmentof U k at at Max k.Bundle Number (wt% U-235) (kg)' (kg) 201C 15 GWd/MT (GWd/ST)GE14-PI OSNAB417-i5GZ-120T-150-T6-3028. (GEI4C) 3 Q2802 GE14-PIOSNAB4 18-14GZ-120T-150-T6-3027 (GEI4C) 3027 GE 14-P 10SNAB418-15GZ-120T-150-T6-3029 (GE I4C)GEI4-PI OSNAB422-1 3GZ-120T-150-T6-3031 (GE14C)GEI4-PI0SNAB422-15GZ-3025 120T-150-T6-3025 (GE14C) _GE 14-P 10SNAB4 19-14GZ-120T-150-T6-3030 (GE14C) 3030 GE I 4-PI OSNAB4 13-16GZ- 3026 120T-150-T6-3026 (GEI4C)GEI4-PIOSNAB418-15GZ--
3240 120T- I 50-T6-3240 (GE I 4C)GE14I-PIOSCOB405-13GZ-3243 120T- 150-T6-3243 (GE 141)GE 14-P 1 OSNAB418-15GZ-120T- 150-T6-3242 (GE I4C)GE I 4-P] OSNAB422-13GZ-120T- 150-T6-3239 (GE I4C)GE I 4-PI OSNAB418-15GZ-120T-150-T6-3241 (GEI4C)GE14-P1OSNAB420-15GZ-120T- 150-T6-2870 (GE I4C)GE 14-P 1 OSNAB419-14GZ-120T-150-T6-2871 (GEI4C) 2 15 Maximum lattice k6,tfor the most reactive* uncontrolled state plus a [[1] adder for uncertainties. Page 19 COLR Page 43 of 57 CLIC13 Core Operating Limits Report Non-Proprietary Information submitted in Accordance with 10 CFR 2.390 Clinton Non-Proprietary Information Reload 12 Class I DOC ID: COLR Clinton 1 Rev. 5 Appendix A 0000-0099-4244-FBIR-NP Rev.ision 0 4F]]Figure B-1 Enrichment and Gadolinium DiStribution for EDB No. 3028 Fuel Bundle GE14-PiOSNAB417-15GZ-120T-150-T6-3028 (GE14C)Page 20 COLR Page 44 of 57 CLIC13 Core Operating Limits Report Non-Proprietary Information submitted in Accordance with 10 CFR 2.390 DOC ID: COLR Clinton 1 Rev. 5 Appendix A 0000-0099-4244-FBIR-NP Revision 0 Clinton Reload 12 Non-Proprietary Information Class I[[1],Figure B-2. Enrichment apnd Gadolinium Distribution for EDB No. 3027Fuel Bundle GE14-P1OSNAB418-14GZ-120T-150-T6-3027 (GE14C)Page 21 COLR Page 45 of 57 CL1C13 Core Operating Limits Repo Non-Proprietary Information submitte Accordance with 10 CFR 2.390 Clinton Reload 12 DOC ID: COLR Clinton 1 Rev. 5 Appendix A 0000-0099-4244-FBIR-NP Revision 0 Non-Proprietary Information Class I[[Figure B-3 Enrichment and Gadolinium Distribution for'EDB No. 3029 Fuel Bundle GE14-PiOSNAB418-15GZ-120T-150-T6-3029 (GE14C)Page 22 COLR Page 46 of 57 CL1C13 Core Operating Limits Repo Non-Proprietary Information submitte Accordance with 10 CFR 2.390 Clinton Reload 12 DOC ID: COLR Clinton 1 Rev. 5 Appendix A 0000-0099-4244-FBIR-NP Revision 0 Non-Proprietary Information Class I Figure B-4 Enrichment and Gadolinium Distribution for EDB No. 3031"Fuiel Bundle.GE14-P1OSNAB422-13GZ-120T-150-T6-3031 (GE14C)Page 23 COLR Page 47 of 57 CLLC13 Core Operating Limits Repc Non-Proprietary Information submittE Accordance with 10 CFR 2.390 Clinton Reload 12 DOC ID: COLR Clinton 1 Rev. 5 Appendix A 0000-0099-4244-F BIR-NP Revision 0 Non-Proprietary Information Class I]]Figure B-5 Enrichment.and Gadolinium
- Distribution for EDB No. 3025 Fuel Bundle GE14-P1OSNAB422-15GZr12OT-150-T6-3025
- (GE14C)Page 24 COLR Page 48 of 57 CL1C13 Core Operating Limits Repc Non-Proprietary Information submittE Accordance with 10 CFR 2.390 Clinton Reload 12 DOC ID:'COLR Clinton 1 Rev. 5 Appendix A 0000-0099-4244-FBIR-NP Revision 0 Non-Proprietary Information Class I'Figure B-6 Enrichment'and Gadolinium Distribution for EDB No. 3030 Fuel Bundle GEI4-P1OSNAB419-14GZ-ý120T-150-T6-3030 (GE14C)Page 25 COLR Page 49 of 57 CL1C13 Core Operating Limits Repc Non-Proprietary Information submitte Accordance with 10 CFR 2.390 Clinton Reload 12 DOC ID: COLR Clinton 1 Rev. 5 Appendix A 0000-0099-4244-FBIR-NP Revision 0 Non-Proprietary Information Class I Figure B-7 Enrichment and Gadolinium Distribution for EDB No. 3026 , Fuel Bundle GE14-P1OSNAB413-16GZ-120T-150-T6-3026,(GE14C)
Page 26 COLR Page 50 of 57 CLIC13 Core Operating Limits Repo Non-Proprietary Information submitte Accordance with 10 CFR 2.390 Clinton Reload 12 DOC ID: COLR Clinton 1 Rev. 5 Appendix A 0000-0099-4244-FBIR-NP Revision 0 Non-Proprietary Information Class I Figure B-8 Enrichment and Gadolinium Distribution for EDB No. 3240., Fuel Bundle GE14-P1OSNAB418-15GZ-120T-150-T6-3240 (GE14C)Page 27 COLR Page 51 of 57 CLIC13 Core Operating Limits Report Non-Proprietary Information submitted in Accordance with 10 CFR 2.390 Clinton Nor Relnad 12 DOC ID: COLR Clinton 1 Rev. 5 Appendix A 0000-0099-4244-FBIR-NP Revision 0 9 i-Proprietary Information Class I Figure B-9 Enrichment and Gadolin'ium Distribution for EDB No. 3243*Fuel Bundle GE141-P1OSCOB405-13GZ-120T-150-T6-3243 (GE14I)Page 28 COLR Page 52 of .57 CL1C13 Core Operating Limits Report Non-Proprietary Information submitted in Accordance with 10 CFR 2.390 Clinton Non-Proprietary Information Reload 12 Class I DOC ID: COLR Clinton 1 Rev. 5 Appendix A 0000-0099-4244-FBIR-NP Revision 0 1]Figure B-10 Enrichment axid- Gadolinium. Distribution for EDB No. 3242 Fuel Bundle GE14-P1OSNAB418-15GZ-120T-150-T6-3242 (GE14C)Page 29 COLR Page 53 of 57 CL1C13 Core Operating Limits Repo Non-Proprietary Information submitte Accordance with 10 CFR 2.390 Clinton Reload 12 DOC ID: COLR Clinton 1 Rev. 5 Appendix A 0000-0099-4244-FBIR-NP Revision 0 S Non-Proprietary Information Class I 1]Figure B-11 Enrichment and Gadolinium-Di~tribution for EDBNo. 3239 Fuel Bundle GE14-PlOSNAB422-l3GZ-120T-150-T6-3239 (GE14C)Page 30 COLR Page 54 of 57 CLI C1 3 Core Operating Limits Report Non-Proprietary Information submitted in Accordance with 10 CFR 2.390 Clinton -Non-Proprietary Information Reload 12- Class I DOC ID: COLR Clinton 1 Rev. 5 Appendix A 0000-0099-4244-FBIR-NP Revision 0 1]Figure B-12 Enrichment and.Gadolinium Distribution for EDB No. 3241 a. Fuel Bundle GE14-P1OSNAB418-15GZ-120T-150-T6-3241 (GE14C)Page 31 COLR Page 55 of 57 CL1C13 Core Operating Limits Repc Non-Proprietary Information submitte Accordance with 10 CFR 2.390 Clinton Reload 12 DOC ID: COLR Clinton 1 Rev. 5 Appendix A 0000-0099-4244-FBIR-NP Revision 0-p Non-Proprietary Information Class I.Figure B-13. Enrichment.and GadoliniumDistribution for EDBNo. 2870 Fuel Bundle GE14-P1OSNAB420-15GZ-120T-150-T6-2870 (GE14C)Page 32 COLR Page 56.of 57 CL1C13 Core Operating Limits Report S., ">' Non-Proprietary Information submitted in Accordance with 10 CFR 2.390 Clinton Non-Proprietary Information Reload 12 Class I DOC ID: COLR Clinton 1 Rev. 5 Appendix A 0000-0099-4244-FBIR-NP Revision 0 Figure B-14 Enrichnient and Gadolinium'Distribution for EDB No. 2871 Fuel Bundle (GE14C)Page 33 COLR Page 57 of 57}}