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{{Adams
#REDIRECT [[U-604284, Core Operating Limits Report for Cycle 17, Revision 11]]
| number = ML16173A269
| issue date = 06/16/2016
| title = Clinton Power Station, Unit 1 - Core Operating Limits Report for Cycle 17, Revision 11
| author name = Stoner T R
| author affiliation = Exelon Generation Co, LLC
| addressee name =
| addressee affiliation = NRC/Document Control Desk, NRC/NRR
| docket = 05000461
| license number = NPF-062
| contact person =
| case reference number = U-604284
| document type = Fuel Cycle Reload Report, Letter
| page count = 29
}}
 
=Text=
{{#Wiki_filter:Clinton Power Station 8401 Power Road Clinton, IL 61727 U-604284 June 16, 2016 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 Azv'iV Exelon*Generation
 
==Subject:==
Submittal of the Core Operating Limits Report for Clinton Power Station, Unit 1, Cycle 17, Revision 11 In accordance with Technical Specification 5.6.5, Core Operating Limits Report (COLR), Item d., Exelon Generation Company (EGC), LLC is submitting Revision 11 of the COLR for Clinton Power Station, Unit 1, Cycle 17. Should you have any questions concerning this report, please contact Mr. Dale Shelton at (217) 937-2800. Respectfully, Theodore R. Stoner Site Vice President Clinton Power Station DRA/cas
 
==Attachment:==
Core Operating Limits Report for Clinton Power Station Unit 1, Cycle 17, Revision 11 cc: NRG Regional Administrator, Region Ill NRG Senior Resident Inspector -Clinton Power Station ATTACHMENT Core Operating Limits Report for Clinton Power Station Unit 1, Cycle 17, Revision 11 Exelon Nuclear -Nuclear Fuels CL1C17 Core Operating Limits Report DOC ID: COLR Clinton i Rev. 11 CORE OPERA TING LIMITS REPORT Prepared By: Reviewed By: Reviewed By: Reviewed By: Approved By: Station Qualified Reviewer By: FOR CLINTON POWER STATION UNIT 1CYCLE17 Date: 04/28/2016 Dale M. Bradish Date: -----RE Reviewer -Christian Small Date: 04/29/16 ESA Reviewer -Andy M. Olson Date: 4/29/2016 D 05/09/2016 ate: -----Date: Page 1of27
* Exeion Nuclear -Nuclear Fuels CL iCi7 Sore Operating Limits Report DOC ID: COLR C!inton 1 Rev. i 1 Table of Contents 0.0 Revision History 3 1.0 Terms and Definitions 6 2.0 General Information 8 3.0 MAPLHGR Limits g 4.0 MCPR Limits 11 5.0 Linear Heat Generation Rate Limits 18 6.0 Reactor Protection System (RPS) Instrumentation 24 7.0 Turbine Bypass System Parameters 24 8.0 Stability Protection Setpoints 25 9.0 Modes of Operation 26 10.0 Methodology 27 11.0 References 27 Page 2 of 27 Exelon Nuclear -Nuclear Fuels CUC17 Core Operating Limits Report Revision Rev. 11 DOC iD: COLR Clinton 1 Rev. 11 Revision History Description First issuance for Cycle 17. Page 3 of27 Exelon Nuclear -Nuclear Fuels CL 1 Ci7 Core Operating Limits Report DOC !D: COLR Clinton i Rev.11 List of Tables Page Table 3-1 MAPLHGR Versus Average Planar Exposure 9 Table 3-2 MAPLHGR Single Loop Operation (SLO) Multiplier 10 Table 3-3 MAPLHGR Multiplier for Loss of 'FULL' Feedwater Heating 10 Table 4-1 Operating Limit Minimum Critical Power Ratio 13 Table 4-2 Power Dependent MCPR Limits MCPR(P) and Multipliers K(P) 14 for Base Case and Two or More TBVOOS Table 4-3 Power Dependent MCPR Limits MCPR(P) and Multipliers K(P) 15 for PROOS/PLUOOS Table4-4 Dual Loop Operation (DLO) Flow Dependent MCPR Limits MCPR(F) 16 for Base Case or PROOS/PLUOOS Table 4-5 Single Loop Operation (SLO) Flow Dependent MCPR Limits MCPR(F) 16 for Base Case or PROOS/PLUOOS Table 4-6 Dual Loop Operation (DLO) Flow Dependent MCPR Limits MCPR(F) 17 for Two or More TBVOOS -**-**-**--.. -******** * ** *** Single Loop Operation (SLO) Flow Dependent MCPR Limits MCPR(F) 17 for Two or More TBVOOS Table 5-1 Linear Heat Generation Rate Limits for U02 Rods 19 Table 5-2 Linear Heat Generation Rate Limits for Gad Rods 19 Table 5-3 Power Dependent LHGR Multipliers LHGRFAC(P) 20 Table 5-4 Flow Dependent LHGR Multipliers LHGRFAC(F) for Base Case or 21 PROOS/PLUOOS Table 5-5 Flow Dependent LHGR Multipliers LHGRFAC(F) for Two or More TBVOOS 21 Table 5-6 LHGR Single Loop Operation (SLO) Reduction Factor 21 Page 4 of 27 Exelon Nuclear -Nuclear Fuels DOC !D: COLR Clinton i Rev. 11 CL 1C17 Core Operating Limits Report Table 5-7 Power Dependent LHGR Multipliers LHGRFAC(P) (Loss of 'FULL' 22 Feedwater Heating) Table 5-8 Flow Dependent LHGR Multipliers LHGRFAC(F) for Base Case or 23 PROOS/PLUOOS (Loss of 'FULL' Feedwater Heating) Table 5-9 Flow Dependent LHGR Mu!tipliesr LHGRFAC(F) for Two or More TBVOOS 23 (Loss of 'FULL' Feedwater Heating) Table 7-1 Reactor Power Limitation -Turbine Bypass Valves Out of Service 24 Table 8-1 OPRM PBDA Trip Setpoint 25 Table 9-1 Modes of Operation 26 Page 5 of 27 Exelon Nuclear -Nuclear Fuels CLiG17 Core Operating Limits Report DOC ID: COLR Clinton i Rev. ii 1.0 Terms and Definitions Base Case Coastdown A case analyzed with two (2) Safety-Relief Valves Out-of-Service (OOS), one {1) Turbine Contml Valve stuck closed, one (1) Turbine Stop Valve stuck closed, one (1) Turbine Bypass Valve OOS, and up to a 50°F feedwater temperature reduction (FWfR includes feedwater heater OOS or final feedwater temperature reduction) at any point in the cycle operation in Dual Loop mode (Reference 3). The reactor condition where thermal power gradually decreases due to fuel depletion while the following conditions are met: 1) all operable control rods are fully withdrawn and 2) all cycle extension techniques have been exhausted including FFWTR and ICF. Design NORMAL Nominal operating temperature for Clinton is 430°F at rated power. Temperature DLO EOOS FFWTR FWHOOS ICF LHGR LHGRFAC(F) LHGRFAC(P) Loss of 'FULL' Feedwater Heating MAPLHGR MCPR MCPR(F) MCPR(P) MELLLA MSJV Dual Reactor Recirculation Loop Operation Equipment Out of Service Final Feedwater Temperature Reduction Feedwater Heaters Out of Service Increased Core Flow Linear Heat Generation Rate LHGR thermal limit flow dependent multipliers LHGR thermal limit power dependent multipliers +/-10 °F outside design NORMAL temperature, meaning changes in feedwater temperature greater than 10 °F and less than or equal to 50 °F. This condition may also be referred to as Asymmetric Feedwater Temperature Operation or AFTO. Maximum Average Planar Linear Heat Generation Rate Minimum Critical Power Ratio MCPR thermal limit flow dependent adjustments and multipliers MCPR thermal limit power dependent adjustments and multipliers Maximum Extended Load Line Limit Analysis Main Steam Isolation Valve Page 6 of 27 Exe!cn Nuclear -Nuclear Fueis CL1C17 Core Operating Limits Report DOC ID; COLR Clinton 1 Rev. 11 OLMCPR OPRM PBDA PLUOOS PROOS SLO SRVOOS TBVOOS TBSOOS TCV TSV Operating Limit Minimum Critical Power Ratio Oscillation Power Range Monitor Period Based Detection Algorithm Power Load Unbalance Out of Service Pressure Regulator Out of Service Single Reactor Recirculation Loop Operation Safety Relief Valve Out of Service Turbine Bypass Valve(s) Out of Service -valves are not credited for fast opening or for normal pressure control Turbine Bypass System Out of Service Turbine Control Valve Turbine Stop Valve Page 7 of27 Exelon Nuclear* Nuclear Fuels CL 1C*i7 Core Operating Um its Report DOC ID: COLR Clinton 1 Rev. ii 2.0 General Information This report is prepared in accordance with Technical Specification 5.6.5 of Reference 1. Power and flow dependent limits and multipliers are listed for various power and flow levels. Linear interpolation is to be used to find intermediate values. These values have been determined using NRG-approved methodologies presented in Section 10 and are established such that all applicable limits of the plant safety analysis are met The data presented in this report is valid for all licensed operating domains on the operating map. including: .. Maximum Extended Load Line Limit down to 99% of rated core flow during full power operation " Increased Core Flow (lCF) up to i 07% of rated core flow " Final Feedwater Temperature Reduction (FFWfR) up to 50cF during cycle extension operation c Feedwater Heater Out of Service (FWHOOS) up to 50°F feedwater temperature reduction at any time during the cycle prior to cycle extension. Equipment out of service conditions are as defined in Section 1 and Section 9. Page 8 of 27 Exelon Nuclear -Nuclear Fuels DOC !D: COLR Clinton i Rev. 11 CL 1C17 Core Operating Limits Report 3.0 MAPLHGR Limits 3.0 Technical Specification
 
==Reference:==
Sections 3.2.1 and 3.4.1. 3.1
 
== Description:==
Table 3-1 is used to determine the maximum average planar linear heat generation rate (MAPLHGR) limit. 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. For Loss of 'FULL' Feedwater Heating (+/-10 °F outside design NORMAL temperature, meaning changes in feedwater temperature greater than 10 °F and less than or equal to 50 °F), the MAPLHGR limits given in Table 3-1 must be multiplied by a LHGR multiplier provided in Table 3-3. This multiplier accounts for potential feedwater riser flow asymmetries (Reference 7). Table 3-1 MAPLHGR Versus Average Planar Exposure1 (Reference 3) Avg. Planar Exposure MAPLHGR Limit (GWd/ST) (kW/ft) 0.00 13.78 17.15 13.78 60.78 6.87 63.50 5.50 1 Linear interpolation should be used for points not listed in the table. Page 9 of 27 Exelon Nuclear -Nuclear Fuels CL iC17 Core Operating Limits Report DOC ID: COLR Clinton i Rev. ii Table 3-2 MAPLHGR Single Loop Operation (SLO} Multipiier (Reference 3) Fuel Type All Fuel Types MAPLHG SLO Multip 0.760 Table 3-3 MAPLHGR Multiplier for Loss of 'FULL' Feedwater Heating (Reference 7) Fuel Type All Fuel Types I MAPLHGR 1 Multiplier I o.99o Page 10 of 27 Exelon Nuciear -Nuclear Fuels DOC ID: COLR Clinton i Rev. 1 i CL iCi7 Core Operating Limits Report 4.0 MCPR Limits 4.0 Technical Specification
 
==Reference:==
Sections 3.2.2, 3.4.1, and 3.7.6. 4.1
 
== Description:==
The various MCPR limits are described below. 4.1.1 Manual Flow Control MCPR Limits The Operating Limit MCPR (OLMCPR) is determined from either Section 4.1.1.1 or 4.1.1.2, whichever is greater at any given power and flow condition. 4.1.1.1 Power-Dependent MCPR For operation less than 33.3% core thermal power, the MCPR(P} as a function of core thermal power is determined from Table 4-2 or Table 4-3 depending on plant conditions. For operation at greater than or equal to 33.3% core thermal power, the OLMCPR as a function of core thermal power is determined by multiplying the applicable rated condition OLMCPR limit shown in Table 4-1 by the applicable MCPR multiplier K(P) given in Table 4-2 or Table 4-3. 4.1.1.2 Flow-Dependent MCPR Tables 4-4 through 4-7 give the MCPR(F) as a function off!ow based on the applicable plant condition. The limits for dual loop operation are listed in Tables 4-4 and 4-6. The limits for single loop operation are listed in Tables 4-5 and 4-7. The MCPR(F) determined from these tables is the flow dependent OLMCPR. 4.1.2 Automatic Flow Control MCPR Limits Automatic Flow Control MCPR Limits are not provided. Page 11 of 27 Exe!on Nuclear* Nuclear Fuels CL1C17 Core Operating Limits Report 4.1.3 Potion A and Option B DOC !D: COLR Clinton i Rev. 1'l Opiion A and Option B refer to use of scram speeds for establishing MCPR operating iirnits. Option A scram speed is the BVVR/6 Technical Specification scram speed. The Technical Specification scram speeds must be met to utilize the Option A MCPR limits. Cycle-specific reload analyses performed by GNF for Option A MCPR limits utilized a 20% core average insertion time of 0.516 seconds (Reference 6). To utilize the MCPR limits for the Option B scram speed, the cycle average scram insertion time for 20% insertion must satisfy equation 2 in Reference 5 Section 4. If the cycle average scram insertion time does not meet the Option B criteria, the appropriate MCPR value may be determined from a linear interpolation between the Option A and B limits as specified by equation 4 in Reference 5 Section 4. 4. 1.4 Recirculation Flow Control Valve Settings The cycle was analyzed with a maximum core flow runout of 109%; therefore the recirculation flow control valve must be set to maintain core flow fess than 109% (92.105 Mlb/hr) for all runout events (Reference 3). Page 12 of 27 Exelon Nuclear -Nuclear Fuels DOC ID: COLR Clinton 1 Rev. 11 CL 1 Ci"7 Core Operating Um its Report I Notes for Table 4-1: Table 4-1 Operating Limit Minimum Critical Power Ratio (Reference 3) EOOS Option A Option B Combination All Exposures All Exposures Base Case DLO 1.40 1.30 Base Case SL01 1.43 1.33 PROOS/PLUOOS 1.40 1.36 DLO PROOS/PLUOOS 1.43 1.39 SL01 Two or More 1.44 1.34 TBVOOS DLO Two or More 1.47 1.37 TBVOOS SL01 1. SLO Option A(B) OLMCPR is the transient DLO Option A(B) OLMCPR plus 0.03. Page 13 of 27 I 11 Exelon Nuclear -Nuclear Fuels GL1C1i Core Operating Limlts Report DOC ID: COLR Clinton 1 Rev. 'l i Table 4-2 Power Dependent MCPR Limits MCPR(P} and Multipliers K(P) for Base Case and Two or More TBVOOS 1* 2 [Reference 3) Core Core Thermal Power (%) EOOS Flow(% Combination of 0.0 21.6 <33.3 >33.3 5,43.3 >43.3 go.o >70.0 100.0 Rated) MCPR(P) K(P) Base Case _s.50 2.31 2.31 2.10 DLO 1.617 1.590 1.313 1.212 1.163 1.000 Option A/B > 50 2.46 2.46 2.17 Base Case ::_50 2.34 2.34 2.13 SLO 1.617 1.590 1.313 1.212 1.163 1.000 Option A/B > 50 2.49 2.49 2.20 Two or More 5,50 2.31 2.31 2.10 TBVOOS DLO 1.617 1.590 1.329 1.212 1.163 1.000 Option A/B > 50 2.46 2.46 2.17 Two or More .:::_50 2.34 2.34 2.13 TBVOOS SLO 1.617 1.590 1.329 1.212 1.163 1.000 Option A/B > 50 2.49 2.49 2.20 Notes for Table 4-2: 1. Values are interpolated between relevant power levels. 2. Allowable EOOS conditions are listed in Section 9.0. Page 14 of 27 
----------Exe!on Nuclear -Nuclear Fuels CLiCi7 Core Operating Limits Report DOC ID: COLR Clinton'! Rev. ii Table 4-3 Power Dependent MCPR Limits MCPR(P) and Multipliers K(P) for PROOS/PLUOOS1* 2 (Reference 3) ' Core Core Thermal Power(%) EOOS Flow (% 0.0 21.6 <33.3 >33.3 43.3 60 I >85.0 Combination ' of Rated) MCPR(P) K(P) PROOS/PLUOOS _::50 2.31 2.31 2.10 DLO 1.617 1.590 1.436 1.309 1.090 Option A/B > 50 2.46 2.46 2.17 PROOS/PLUOOS .:: 50 2.34 2.34 2.13 SLO 1.617 1.590 1.436 1.309 1.090 Option A/B > 50 2.49 2.49 2.20 Notes for Table 4-3: 1. Values are interpolated between relevant power levels. 2. Allowable EOOS conditions are listed in Section 9.0. Page 15 of 27 100.0 1.000 1.000 Exelon Nuclear -Nuclear Fuals CL1C17 Co;e Operating Limits Report DOC !D; COLR Clinton 1Rev.11 Table 4-4 Dual Loop Operation (DLO) Flow Dependent MCPR Limits MCPR(F) for Base Case or PROOSfPLUOOS1 {Reference 3) Core Flow MCPR(F) (%rated) 0.0 1.88 25.0 1.70 84.1 1.27 109.0 1.27 Table 4-5 Single Loop Operation (SLO) Flow Dependent MCPR Limits MCPR(F) for Base Case or PROOSfPLUOOS1 (Reference 3) Core Flow MCPR(F} (%rated) 0.0 1.91 25.0 1.73 84.1 1.30 109.0 1.30 1 Linear interpolation should be used for points not listed in the table. Page 16 of 27 Exelon Nuclear -Nuclear Fuels DOC ID: COLR Clinton *1 Rev. ii CL 1Ci7 Core OPBratlng Limits Report Table 4-6 Dual Loop Operation (OLO) Flow Dependent MCPR Limits MCPR(F) for Two or More TBVOOS1 (Reference 3} Core Flow MCPR(F) (%rated) 0.0 2.04 25.0 1.85 100.0 1.27 109.0 1.27 Table 4-7 Single Loop Operation (SLO) Flow Dependent MCPR Limits MCPR(F) for Two or More TBVOOS1 (Reference 3) Core Flow MCPR(F) (%rated) 0.0 2.07 25.0 1.88 100.0 1.30 109.0 1.30 1 Linear interpolation should be used for points not listed in the table. Page 17 of27 Exelon Nuclear* Nuclear Fuels CUC17 Core Operating Limit:; Report 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:==
DOC ID: COLR Ciinton i Rev. 11 The linear heat generation rate (LHGR) fimit is the product of the exposure dependent LHGR limit (from Table 5-1 for U02 fuel rods and Table 5-2 for Gadolinia fuel rods) and the minimum of: the power dependent LHGR Factor, LHGRFAC(P), the flow dependent LHGR Factor, LHGRFAC(F), or the single loop operation (SLO) multiplication factor if applicable. The LHGRFAC(P) is determined from Table 5-3. The LHGRFAC(F) is determined from Tables 5-4 and 5-5, depending on plant conditions. The SLO multiplication factor can be found in Table 5-6. Tables 5-1 and 5-2 are the LHGR limit as a function of peak pellet exposure.
* For Loss of 'FULL' Feedwater Heating (+/-1 O &deg;F outside design NORMAL temperature, meaning changes in feedwater temperature greater than 10 &deg;F and less than or equal to 50 &deg;F), LHGRFAC(P) is determined from Table 5-7 and LHGRFAC(F) is determined from Tables 5-8 and 5-9, depending on plant conditions. Concurrent operation with SLO and reduced feedwater heating has not been evaluated and thus is not a valid operating mode. (Reference 8) Page 18 of 27 Exelon Nuclear* Nuclear Fuels DOC ID: COLR Clinton 1 Rev. 11 CL 1Ci7 Core Operating Limits Report Table 5-1 Linear Heat Generation Rate Limits for U02 Rods1 (References 4 and 9) Fuel Type LHGR Limit GNF2 See Table 8-1 of Reference 9 Table 5-2 Linear Heat Generation Rate Limits for Gad Rods1 (References 4 and 9) el Type GNF2 1 Linear interpolation should be used for points not listed in the table. Page 19 of 27 Exelon Nuclear -Nuclear Fuels CLiC17 Core Operating Limlts Report DOC ID: COLR Clinton i Rev. i 'l Core EOOS Flow Combination (%of Rated) Base Case DLO/SLO > 50 PROOS/PLUOOS .::so DLO/SLO >so Two or More .::so TBVOOS DLO/SLO > 50 Notes for Table S-3: Table 5-3 Power Dependent LHGR Multipliers LHGRFAC(P)1 (Reference 3) Core Thermal Power (%1 0.0 21.6 <33.3 :::_33.3 40.0 43.3 <60.0 2:_60.0 LHGRFAC(P) 0.634 0.634 0.689 0.651 -0.684 --0.572 0.572 0.600 O.S60 0.560 0.560 0.560 O.S60 -0.709 0.749 O.S60 O.S60 O.S60 0.634 0.634 0.689 0.6S1 -0.684 --0.572 0.572 0.600 1. Linear interpolation should be used for points not listed in the table. Page 20 of 27 <85.0 ;:85.0 --0.868 0.906 --' 100.0 1.000 1.000 1.000 E.xe!on Nuclear -Nuclear Fuels CL1C17 Core Operating Limits Report DOC ID: COLR Clinton i Rev. 11 Table 5-4 Flow Dependent LHGR Multipliers LHGRFAC{F) for Base Case or PROOS/PLUOOS1 (Reference 3) I Core Flow LHGRFAC(F) (%rated) 0.0 0.442 25.0 0.612 30.0 0.646 82.2 1.000 109.0 1.000 Table 5-5 Flow Dependent LHGR Multipliers LHGRFAC(F) for Two or More TBVOOS1 (Reference 3) Core Flow LHGRFAC(F) (%rated) 0.0 0.140 25.0 0.365 30.0 0.410 40.0 0.500 50.0 0.630 80.0 0.860 98.3 1.000 109.0 1.000 Table 5-6 LHGR Single Loop Operation (SLO) Reduction Factor (Reference 3) Fuel LHGR Type SLO Multiplier All Fuel Types 0.760 1 Linear interpolation should be used for points not listed in the table. Page 21of27 I Exelon Nuclear* Nuclear Fuels CL*JCi7 Core Operating Limits Report DOC ID: COLR Clinton i Rev. 1i Core EOOS Flow Comblnation (%of Rated) Base Case DLO > 50 PROOS/PLUOOS DLO > 50 Two or More TBVOOS DLO > 50 Notes for Table 5-7: Table 5-7 Power Dependent LHGR Multipliers LHGRFAC(P} (loss of 'FULL' Feedwater Heating}1'2 (.Reference 3) Core Thermal Power (%1 0.0 21.6 <33.3 ::_33.3 40.0 43.3 <60.0 LHGRFAC P) 0.628 0.628 0.682 0.644 -0.677 -0.566 0.566 0.594 0.554 0.554 0.554 0.554 0.554 -0.702 0.554 0.554 0.554 0.628 0.628 0.682 0.644 -0.677 -0.566 0.566 0.594 1. Linear interpolation should be used for points not listed in the table. ::so.a <85.0 ::_85.0 ---0.742 0.859 0.897 ---100.0 0.990 0.990 0.990 2. Concurrent operation with SLO and reduced feedwater heating has not been evaluated and thus is not a valid operating mode {Reference 8). Page22 of27 Exelon Nuclear -Nuclear Fuels DOC ID: COLR Ciir:ton 1 Rev. ii CL 1Ci7 Core Operating Limits Report Table 5-8 Flow Dependent LHGR Multipliers LHGRFAC(F) for Base Case or PROOS/PLUOOS (Loss of 'FULL' Feedwater Heating}1 (Reference 3) Core Flow LHGRFAC{F) (%rated) 0.0 0.438 25.0 0.606 30.0 0.640 82.2 0.990 109.0 0.990 Table 5-9 Flow Dependent LHGR Multipliers LHGRFAC(F) for Two or More TBVOOS (Loss of 'FULL' Feedwater Heating)1 (Reference 3) Core Flow LHGRFAC(F) (%rated) 0.0 0.139 25.0 0.361 30.0 0.406 40.0 0.495 50.0 0.624 80.0 0.851 98.3 0.990 109.0 0.990 1 Linear interpolation should be used for points not listed in the table. Page 23 of 27 Exelon Nuclear -Nuclear Fuels DOC ID: COLR Clinton 1 Rev. 1'1 CLi C17 Core Operating Limits Report 6.0 Reactor Protection System (RPS) Instrumentation 6:1 Technical Specification
 
==Reference:==
Section 3.3.1.1 6.2
 
== Description:==
The Average Power Range Monitor (APRM) flow biased simulated thermal power-high time constant, shall be beti.-veen 5.4 seconds and 6.6 seconds (Reference 6). 7.0 Turbine Bypass System Parameters 7.1 Technical Specification
 
==Reference:==
Section 3. 7.6 7.2
 
== Description:==
The operability requirements for the Main Turbine Bypass System are governed by Technical Specification 3.7 .6. If the requirements of LCO 3. 7.6 cannot be met, the appropriate reactor thermal power, minimum critical power ratio (MCPR), and linear heat generation rate (LHGR) limits must be used to comply with the assumptions in the design basis transient analysis. Table 7-1 provides the reactor thermal power limitations for an inoperable Main Turbine Bypass System as specified in Technical Specification LCO 3.7.6. The MCPR and LHGR limits for one TBVOOS are included in the Base Case, as identified in Table 9-1. The MCPR and LHGR limits for two or more TBVOOS are provided in Sections 4 and 5. Table 7-1 Reactor Power Limitation -Turbine Bypass Valves Out of Service (References 2, 3, and 10) Turbine Bvoass System Status I Maximum Reactor Thermal Power 1% Ratedl One Turbine Bypass Valve I 100.0 Out of Service Two or More Turbine Bypass Valves I 100.0 Out of Service Page 24 of 27 Exe!on Nuclear -Nuclear Fuels CUCi7 Core Operating Limits Report 8.0 Stability Protection Setpoints DOC !D: COLR Ciinton 1 Rev. 'i 1 8.1 Technical Specification
 
==Reference:==
Section 3.3.1.3 8.2
 
== Description:==
The OPRM Period Based Detection Algorithm (PBDA) Trip Setpoint for the OPRM System for use in Technical Specification 3.3.1.3 is found in Table 8-1. This value is based on the cycle specific analysis documented in Reference 3. Stability-based OLMCPR is non-limiting for the PBDA setpoint in Table 8-1. Table 8-1 OPRM PBDA Trip Setpoint (Valid for All Conditions) (Reference 3) PBDA Trip Amplitude Corresponding Maximum Confirmation Count Tri Settin 1.12 14 Page 25 of 27 Exelon Nuclear -Nuclear Fuels CLiC17 Core Operating Limits Report 9.0 Modes of Operation DOC ID: COLR Clinton 1 Rev. 11 The Allowed Modes of Operation with combinations of Equipment Out-of-Service (EOOS) are as described below in Table 9-1: EOOS Options2 Base Case DL03 Base Case SL01'3 I PROOS/PLUOOS DL03*5 PROOS/PLUOOS SL01*3*5 Two or More TBVOOS DL04 Two or More TBVOOS SL01*4 Notes: Table 9-1 Modes of Operation (Reference 3) Operating Region Standard I MELLLA !CF I Yes I Yes Yes Yes I No No Yes I Yes Yes Yes I No No Yes I Yes Yes Yes I No No FFWTR1 Coastdown Yes Yes No Yes Yes Yes No Yes Yes Yes No Yes 1. Concurrent operation with SLO and Loss of 'FULL' Feedwater Heating (+/-10 &deg;F outside design NORMAL temperature, meaning changes in feedwater temperature greater than 10 &deg;F and less than or equal to 50 &deg;F). MELLLA, ICF, or FFWfR has not been evaluated and thus is not a valid operating mode. (Reference 8) 2. A single Main Steam Isolation Valve (MSIV) out of service is supported at or below 75% power. (Reference 3) 3. Includes 2 SRVOOS, 1 TCV stuck closed, 1 TSV stuck ciosed, 1 TBVOOS, and up to a 50&deg;F feedwater temperature reduction (FWTR includes feedwater heater OOS or final feedwater temperature reduction) at any point in cycle operation in Dual Loop mode. 4. Includes 2 SRVOOS and up to a 50&deg;F feedwater temperature reduction (FWfR includes feedwater heater OOS or final feedwater temperature reduction) at any point in cycle operation in Dual Loop mode. 5. Concurrent operation with either or both of PROOS + PLUOOS is allowed. Page 26 of 27 Exeion Nuclear -Nuclear Fuels CUC17 Core Operating Um its Report 10.0 Methodology DOC ID: COLR Ciinton 1 Rev. i 1 The analytical methods used to determine the core operating Hmits shall be those previously reviewed and approved by the NRC, specifically those described in the following documents: 1. Global Nuclear Fuel Document, "General Electric Standard Application for Reactor Fuel", NEDE-24011-P-A-22-US, November 2015 and U.S. Supplement NEDE-24011-P-A-22-US, November 2015. 11.0 References 1. Nuclear Regulatory Commission, Technical Specifications for Clinton Power Station Unit 1, Docket No. 50-461, License No. NPF-62. 2. GE Hitachi Nuclear Energy Report, 0000-0086-4634-R2-P Revision 1, "Clinton Power Station One Bypass Out of Service or Turbine Bypass System Out of Service Analysis-Final", July 2010. 3. Global Nuclear Fuel Document, 002N6802 Revision 0, "Supplemental Reload Licensing Report for Clinton Unit 1 Reload 16 Cycle 17", March 2016. 4. Global Nuclear Fuel Document, 002N6803 Revision 0, "Fuel Bundle Information Report for Clinton Unit 1 Reload 16 Cycle 17", March 2016. 5. General Electric Document, GE-NE-0000-0000-7456-01P, "Option B Scram Times For Clinton Power Station", February 2002. 6. Exelon Transmittal of Design Information, TOOi ES1500028 Revision 0, "Clinton Unit 1 Cycle 17 Final Resolved OPL-3 Parameters". November 24, 2015. 'T -GE RitachiNUclea'fEnergy Letter, CFL-EXN-LH1-12-059, "Affirmation of the Clinton Power Station Unit 1 MAPLHGR Reduction for Feedwater Riser Flow Asymmetry", April 25, 2012. 8. General Electric Document, GE-NE-0000-0026-1857-R1Revision1, "Evaluation of Operation With Equipment Out-Of-Service for the Clinton Power Station", June 28, 2004. 9. Global Nuclear Fuel Document, NEDC-33270P, Rev. 5, "GNF2 Advantage Generic Compliance with NEDE-24011-PA (GESTAR-11)", May 2013. 10. GE Hitachi Nuclear Energy Report, 003N4558-RO, "Removal of TBSOOS Power Restriction for Clinton", March 10, 2016. Page 27 of 27 
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