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{{Adams
#REDIRECT [[U-604458, Submittal of the Core Operating Limits Report, Cycle 19, Revision 14]]
| number = ML18354A732
| issue date = 12/18/2018
| title = Submittal of the Core Operating Limits Report, Cycle 19, Revision 14
| 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-604458
| document report number = COLR Clinton 1 Rev. 14
| document type = Fuel Cycle Reload Report, Letter
| page count = 28
}}
 
=Text=
{{#Wiki_filter:Clinton Power Station 8401 Power Road Clinton, IL 61727 U-604458 December 18, 2018 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 19, Revision 14 In accordance with Technical Specification 5.6.5, Core Operating Limits Report (COLR), Item d., Exelon Generation Company (EGC), LLC is submitting Revision 14 of the COLR for Clinton Power Station, Unit 1, Cycle 19. There are no regulatory commitments contained in this letter. Should you have any questions concerning this report, please contact Mr. Dale Shelton at (217) 937-2800.
* Respectfully, Theodore R. Stoner Site Vic!3 President Clinton Power Station TRS/grs
 
==Attachment:==
 
Core Operating Limits Report for Clinton Power Station Unit 1, Cycle 19, Revision 14 cc: NRC Regional Administrator, Region Ill NRC Senior Resident Inspector
-Clinton Power Station ATTACHMENT Core Operating Limits Report for Clinton Power Station Unit 1, Cycle 19 Revision 14 Exelon Nuclear -Nuclear Fuels DOC ID: COLR Clinton 1 Rev. 14 CL 1C19 Core Operating Limits Report CORE OPERATING LIMITS REPORT FOR CUNTON POWER STATION UNIT 1 CYCLE 19 Prepared By: Date: 11 /6/18 Kevin Smith Reviewed By: Date: If-"8-I£ ie Heugel Date: 11/8/2018 Reviewed By: Date: 11/8/18 Approved By: f'\i:~.MCcoskeyfocAJoMsoa Date: 11/14/2018 NF'Manager
-rmando Johnson ,. Station Qualified r7>,}lf 11 _J) Reviewer By: _\J_'.*~ -'***~'""'*
~=---=~.._..__*
------Page 1 of26 Date~ 11-JY-J g ,,
Exelon Nuclear -Nuclear Fuels CL1C19 Core Operating Limits Report Revision History List of Tables 1.0 Terms and Definitions
 
===2.0 General===
Information
 
===3.0 MAPLHGR===
Limits 4.0 MCPR Limits Table of Contents 5.0 Linear Heat Generation Rate Limits 6.0 Reactor Protection System (RPS) Instrumentation 7 .0 Turbine Bypass System Parameters
 
===8.0 Stability===
 
Protection Setpoints
 
===9.0 Modes===
of Operation 10.0 Methodology 11.0 References Page 2 of 26 DOC ID: COLR Clinton 1 Rev. 14 3 4 6 8 9 11 17 23 23 24 25 26 26 Exelon Nuclear -Nuclear Fuels CL 1C19 Core Operating Limits Report Revision Rev. 13 Rev. 14 DOC ID: COLR Clinton 1 Rev. 14 Revision History Description Page 3 of 26 First issuance for Cycle 19 Second issuance for Cycle 19 due to TRACG-AOO implementation Exelon Nuclear -Nuclear Fuels DOC ID: COLR Clinton 1 Rev. 14 CL 1C19 Core Operating Limits Report 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 12 Table 4-2 Power Dependent MCPR Limits MCPR(P) and Multipliers K(P) 13 for Base Case and Two or More TBVOOS Table 4-3 Power Dependent MCPR Limits MCPR(P) and Multipliers K(P) 14 for PROOS/PLUOOS Table 4-4 Dual Loop Operation (DLO) Flow Dependent MCPR Limits MCPR(F) 15 for Base Case or PROOS/PLUOOS Table 4-5 Single Loop Operation (SLO) Flow Dependent MCPR Limits MCPR(F) 15 for Base Case or PROOS/PLUOOS Table 4-6 Dual Loop Operation (DLO) Flow Dependent MCPR Limits MCPR(F) 16 for Two or More TBVOOS Table 4-7 Single Loop Operation (SLO) Flow Dependent MCPR Limits MCPR(F) 16 for Two or More TBVOOS Table 5-1 Linear Heat Generation Rate Limits for U02 Rods 18 Table 5-2 Linear Heat Generation Rate Limits for Gad Rods 18 Table 5-3 LHGR Single Loop Operation (SLO) Multiplier 18* Table 5-4 Power Dependent LHGR Multipliers LHGRFAC(P) for Base Case or Two or 19 MoreTBVOOS Table 5-5 Power Dependent LHGR Multipliers LHGRFAC(P) for PROOS/PLUOOS 19 Table 5-6 Flow Dependent LHGR Multipliers LHGRFAC(F) for Base Case or PROOS/PLUOOS 20 Table 5-7 Flow Dependent LHGR Multipliers LHGRFAC(F) for Two or More TBVOOS 20 Page4 of 26 Exelon Nuclear -Nuclear Fuels DOC ID: COLR Clinton 1 Rev. 14 CL 1C19 Core Operating Limits Report Table 5-8 Power Dependent LHGR Multipliers LHGRFAC(P) for Base Case or Two 21. or More TBVOOS (Loss of 'FULL' Feedwater Heating) Table 5-9 Power Dependent LHGR Multipliers LHGRFAC(P) for PROOS/PLUOOS 21 (Loss of 'FULL' Feedwater Heating) Table.5-10 Flow Dependent LHGR Multipliers LHGRFAC(F) for Base Case or 22 PROOS/PLUOOS (Loss of 'FULL' Feedwater Heating) Table 5-11 Flow Dependent LHGR Multipliers LHGRFAC(F) for Two or More TBVOOS 22 (Loss of 'FULL' Feedwater Heating) Table 7-1 Reactor Power Limitation
-Turbine Bypass Valves Out of Service 23 Table 8-1 OPRM PBDA Trip Setpoint (Valid for All Conditions) 24 Table 9-1 Modes of Operation 25 Page 5 of 26 Exelon Nuclear -Nuclear Fuels DOC ID: COLR Clinton 1 Rev. 14 CL 1C19 Core Operating Limits Report 1.0 Terms and Definitions AFTO Asymmetric Feedwater Temperature Operation Base Case Coastdown A case analyzed with two (2) Safety-Relief Valves Out-of-Service (OOS), one (1) Turbine Control Valve stuck closed, one (1) Turbine Stop Valve stuck closed, one (1) Turbine Bypass Valve OOS, and up to a 50°F feedwater temperature reduction (FWfR includes feedwater heater OOS or final feedwater temperature reduction) at any point in the cycle operation in Dual Loop mode (Reference 12). 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 FFWfR and ICF. Design NORMAL Nominal operating temperature for Clinton is 430°F at rated power. Temperature DLO EOOS FWfR FFWfR FWHOOS ICF LCO LHGR LHGRFAC(F)
LHGRFAC(P)
Loss of 'FULL' Feedwater Heating MAPLHGR MCPR MCPR(F) Dual Reactor Recirculation Loop Operation Equipment Out of Service Feedwater Temperature Reduction, including FFWfR or feedwater heater OOS Final Feedwater Temperature Reduction Feedwater Heaters Out of Service Increased Core Flow Limiting Condition of Operation Linear Heat Generation Rate LHGR thermal limit flow dependent multipliers LHGR thermal limit power dependent multipliers
'FULL' Feedwater heating is temperature within .+/-.1 O °F of design NORMAL temperature.
The Loss of 'FULL' Feedwater Heating constitutes a change in temperature greater than 10 °F, but less than or equal to 50 °F FWfR. This condition accounts for effects of 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 Page 6 of 26 Exelon Nuclear -Nuclear Fuels DOC ID: COLR Clinton 1 Rev. 14 CL 1C19 Core Operating Limits Report MCPR(P) MELLLA MSIV OLMCPR oos OPRM PBDA PLUOOS PROOS SLO SRVOOS TBVOOS TBSOOS TCV TSV MCPR thermal limit power dependent adjustments and multipliers . Maximum Extended Load Line Limit Analysis Main Steam Isolation Valve Operating Limit Minimum Critical Power Ratio Out of Service* 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 of 26 Exelon Nuclear -Nuclear Fuels DOC ID: COLR Clinton 1 Rev.14 CL 1C19 Core Operating Limits Report 2.0 General Information This report is prepared in accordance with Technical Specification 5.6.5 of Reference
: 1. Power and flow dependent limits and multipliers are listed for various power and flow levels. Linear interpolation is to be used to find intermediate values. These values have been determined using NRC-approved methodologies presented in Section 10 and are established such that all applicable limits of the plant safety analysis are met. The data presented in this report is valid for all licensed operating domains on the operating map, including:
* Maximum Extended Load Line Limit down to 99% of rated core flow during. full power operation
* Increased Core Flow (ICF) up to 107% of rated core flow
* Final Feedwater Temperature Reduction (FFWTR) up to 50°F during cycle extension operation
* 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 defi.ned in Section 1 and Section 9. Page 8 of 26 Exelon Nuclear -Nuclear Fuels CL 1C19 Core Operating Limits Report 3.0 MAPLHGR Limits 3.1 Technical Specification
 
==Reference:==
 
*sections 3.2.1 and 3.4.1. 3.2
 
== Description:==
 
DOC ID: COLR Clinton 1 Rev. 14 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 (a change in temperature greater than 10 °F, but less than or equal to 50 °F FWTR), the MAPLHGR limits given in Table 3-1 must be multiplied by a MAPLHGR multiplier provided in Table 3-3. This multiplier accounts for potential feedwater riser flow asymmetries (Reference 7). Table 3-1 MAPLHGR Versus Average Planar Exposure 1 (Reference
: 3) . 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 26 Exelon Nuclear -Nuclear Fuels DOC ID: COLR Clinton 1 Rev. 14 CL 1C19 Core Operating Limits Report Table 3-2 MAPLHGR Single Loop Operation (SLO) Multiplier (Reference
: 3) Fuel MAPLHGR Type SLO Multiplier GNF2 0.760 Table 3-3 MAPLHGR Multiplier for Loss of 'FULL' Feedwater Heating (Reference
: 7) Fuel MAPLHGR Type Multiplier GNF2 0.990 Page 10 of 26 Exelon Nuclear -Nuclear Fuels CL1C19 Core Operating Limits Report 4.0 MCPR Limits 4.1 Technical Specification
 
==Reference:==
 
Sections 3.2.2, 3.4.1, and 3.7.6.
4.2
 
== Description:==
 
DOC 10: COLR Clinton 1 Rev. 14 The Operating Limit MCPR (OLMCPR) is determined from either Section 4.2.1 or 4.2.2, whichever is greater at any given power and flow condition.
4.2.1 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 determined from Table 4-2 or Table 4-3 depending on plant conditions.
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 or Table 4-3. 4.2.2 Flow-Dependent MCPR Tables 4-4 through 4~7 give the MCPR(F) as a function of flow based on the applicable plant condition.
The limits for dual loop operation are listed in Tables 4-4 and 4-6. The limits for single loop operation are listed in Tables 4-5 and 4-7. The MCPR(F) _determined from these tables is the flow dependent OLMCPR. 4.2.3 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. 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. 4.2.4 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 less than 109% (92.105 Mlb/hr) for all runout events (Reference 3). Page 11 of 26 Exelon Nuclear -Nuclear Fuels DOC ID: COLR Clinton 1 Rev. 14 CL 1C19 Core Operating Limits Report Table 4-1 Operating Limit Minimum Critical Power Ratio 1 (Reference
: 3) EOOS Option A Option B Combination All Exposures All Exposures Base Case DLO 1.32 1.28 Base Case SLO 1 1.35 1.31 PROOS/PLUOOS 1.50 1.50 DLO PROOS/PLUOOS 1.53 1.53 SL0 1 Two or More 1.39 1.35 TBVOOS DLO Two or More 1.42 1.38 TBVOOS SL0 1 1 SLO Option A(B) OLMCPR is the transient DLO Option A(B) OLMCPR plus 0.03 (Reference 3). Page 12 of 26 Exelon Nuclear -Nuclear Fuels DOC ID: COLR Clinton 1 Rev. 14 CL 1C19 Core Operating Limits Report 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) EOOS Core Flow Core Thermal Power(%) Combination
(% of 0.0 21.6 S33.3 >33.3 <43.3
*Rated) MCPR(P) < 50 1.97 1.97 1.92 Base Case DLO 1.391 1.391 Option NB ;;;: 50 2.04 2.04 2.02 < 50 2.00 2.00 1.95 Base Case SLO 1.391 1.391 Option NB ;;;: 50 2.07 2.07 2.05 Two or More < 50 1.97 1.97 1.92 TBVOOS DLO 1.391 1.391 Option A/B ;;;: 50 2.04 2.04 2.02 Two or More < 50 2.00 2.00 1.95 TBVOOS SLO 1,.391 1.391 Option NB ;;;: 50 2.07 2.07 2.05 ' 1 Linear interpolation should be used for points not listed in the table. 2 Allowable EOOS conditions are listed in Section 9.0. Page 13 of 26 >43.3 60 <70.0 K(P) 1.296 1.239 1.205 1.296 1.239 1.205 1.296 1.239 1.205 1.296 1.239 1.205 >70.0 85 100 1.122 1.051 1.000 1.122 1.051 1.000 1.122 1.051 1.000 1.122 1.051 1.000 Exelon Nuclear -Nuclear Fuels CL1C19 Core Operating Limits Report DOC ID: COLR Clinton 1 Rev. 14 Table 4-3 Power Dependent MCPR Limits MCPR(P) and Multipliers K(P) for PROOS/PLUOOS 1*2 (Reference
: 3) Core Flow S33. EOOS Combination
(% of 0.0 21.6 3. >33.3 Rated) MCPR(P) PROOS/PLUOOS
< 50 1.97 1.97 1.92 DLO 1.391 Option A/B 50 2.04 2.04 2.02 PROOS/PLUOOS
< 50 2.00 2.00 1.95 SLO 1.391 Option A/B 50 2.07 2.07 2.05 lLinear interpolation should be used for points not listed in the table. 2 Allowable EOOS conditions are listed in Section 9.0. Page 14 of 26 Core Thermal Power(%) 43.3 60 70 ~85.0 K(P) 1.391 1.347 1.253 1.076 1.391 1.347 1.253 1.076 >85.0 1.060 1.060 100.0 1.000 1.000 Exelon Nuclear -Nuclear Fuels DOC ID: COLR Clinton 1 Rev. 14 CL 1C19 Core Operating Limits Report Table 4-4 Dual Loop Operation (DLO) Flow Dependent MCPR Limits MCPR(F) for Base Case or PROOS/PLUOOS 1 (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 PROOS/PLUOOS 1 (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 15 of 26 Exelon Nuclear -Nuclear Fuels DOC ID: COLR Clinton 1 Rev. 14 CL 1C19 Core Operating Limits Report Table 4-6 Dual Loop Operation (DLO) Flow Dependent MCPR Limits MCPR(F) for Two or More TBVOOS 1 (Reference
: 3) Core Flow MCPR(F) (% rated) 0.0 2.04 25.0 1.85 100.0 1.27 109.0 1.27 Table4-7 Single Loop Operation (SLO) Flow Dependent MCPR Limits MCPR(F) for Two or More TBVOOS 1 (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 16 of 26 Exelon Nuclear -Nuclear Fuels CL1C19 Core Operating Limits 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 Clinton 1 Rev. 14 The lfnear 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 Multiplier, LHGRFAC(P), the flow dependent LHGR Multiplier, LHGRFAC(F), or the single loop operation (SLO) Multiplier if applicable.
The SLO multiplier can be found in Table 5-3. The LHGRFAC(P) is determined from Table 5-4 and 5-5. The LHGRFAC(F) is determined from Tables 5-6 and 5-7, depending on plant conditions.
Tables 5-1 and 5-2 are the LHGR limit as a function of peak pellet exposure.
For Loss of 'FULL' Feedwater Heating (a change in temperature greater than 10 &deg;F, but less than or equal to 50 &deg;F FWTR), LHGRFAC(P) is determined from Table 5-8 and 5-9, LHGRFAC(F) is determined from Tables 5-10 and 5-11, depending on plant conditions.
Concurrent operation with SLO and reduced feedwater heating has not been evaluated and thus is not a valid operating mode. (Reference
: 8) Page 17 of 26 Exelon Nuclear -Nuclear Fuels DOC ID: COLR Clinton 1 Rev. 14 CL 1C19 Core Operating Limits Report Table 5-1 Linear Heat Generation Rate Limits for U02 Rods 1 (References 4 and 9) Fuel Type GNF2 LHGR Limit See Table B-1 of Reference 9 Table 5-2 Linear Heat Generation Rate Limits for Gad Rods 1 (References 4 and 9) Fuel Type GNF2 LHGR Limit See Table B-2 of Reference 9 Table 5-3 LHGR Single Loop Operation (SLO) Multiplier (Reference
: 3) Fuel LHGR Type SLO Multiplier GNF2 0.76n 1 Linear interpolation should be used for points not listed in the table. Page 18 of 26 Exelon Nuclear -Nuclear Fuels DOC ID: COLR Clinton 1 Rev. 14 CL 1C19 Core Operating Limits Report , Table 5-4 Power Dependent LHGR Multipliers LHGRFAC(P) for Base Case or Two or More TBVOOS 1 (Reference
: 3) EOOS Combination Base Case DLO/SLO I Two or More TBVOOS DLO/SLO Core Core Thermal Power(%) Flow 0.0 21.6 S33.3 >33.3 S43.3 >43.3 60.0 70.0 (% of Rated) LHGRFAC(P)
< 50 0.660 0.660 0.755 0.720 0.775 0.815 0.930 0.975 ;;;: 50 0.635 0.635 0.720
< 50 0.660 0.660 0.755 0.720 0.775 0.815 0.930 0.975 ;;;: 50 0.635 0.635 0.720 Table 5-5 Power Dependent LHGR Multipliers LHGRFAC(P) for PROOS/PLUOOS 1 * (Reference
: 3) Core Core Thermal Power(%) 85.0 1.000 1.000 100 1.000 1.000 EOOS Flow 0.0 21.6 S33.3 >33.3 '43.3 60.0 70.0 85.0 100.0 Combination
(% of Rated) LHGRFAC(P)
PROOS/PLUOOS
< 50 0.660 0.660 0.755 DLO/SLO 0.720 0.775 0.930 0.975 0.975 1.000 ;;;: 50 0.635 0.635 0.720 1 Linear interpolation should be used for points not listed in the table. Page 19 of 26 Exelon Nuclear -Nuclear Fuels DOC ID: COLR Clinton 1 Rev. 14 CL 1C19 Core Operating Limits Report Table 5-6 Flow Dependent LHGR Multipliers LHGRFAC(F) for Base Case or PROOS/PLUOOS 1 (Reference
: 3) 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 5-7 Flow Dependent LHGR Multipliers LHGRFAC(F) for Two or More TBVOOS 1 (Reference
: 3) Core Flow LHGR,FAC(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 1 Linear interpolation should be used for points not listed in the table. Page20 of 26 Exelon Nuclear -Nuclear Fuels DOC ID: COLR Clinton 1 Rev. 14 CL 1C19 Core Operating Limits Report Table 5,8 Power Dependent LHGR Multipliers LHGRFAC(P) for Base Case or Two or More TBVOOS (Loss of 'FULL' Feedwater Heating)1*2*3 EOOS Combination Base Case DLO Two or More TBVOOS DLO (Reference
: 3) Core Core Thermal Power(%) Flow 0.0 21.6 ::.33.3 >33.3 ::.43.3 >43.3 60.0 70.0 85.0 (% of Rated) LHGRFAC(P)
< 50 0.653 0.653 0.747 0.713 0.767 0.807 0.921 0.965 0.990 ;;:: 50 0.629 0.629 0.713
< 50 0.653 0.653 0.747 0.713 0.767 0.807 0.921 0.965 0.990
;;: 50 0.629 0.629 0.713 Table 5-9 Power Dependent LHGR Multipliers LHGRFAC(P) for PROOS/PLUOOS (Loss of 'FULL' Feedwater Heating) 1*2*3 (Reference
: 3) Core Core Thermal Power(%) 100 0.990 0.990 EOOS Flow 0.0 21.6 ::.33.3 >33.3 43.3 60.0 70.0 85.0 100.0 Combination
(% of Rated) LHGRFAC(P)
PROOS/PLUOOS
< 50 0.653 0.653 0.747 DLO 0.713 0.767 0.921 0.965 0.965 0.990
;;: 50 0.629 0.629 0.713
: 1. Values in Table 5-8 and 5-9 are determined by applying the required 1 % adjustment from Appendix E of Reference 3 to the values provided in Table 5-4 and 5-5. 2. Linear interpolation should be used for points not listed in the table. 3. Concurrent operation with SLO and reduced feedwater heating has not been evaluated and thus is not a valid operating mode (Reference 8). Page 21 of 26 Exelon Nuclear -Nuclear Fuels DOC ID: COLR Clinton 1 Rev. 14 CL 1C19 Core Operating Limits Report Table 5-10 Flow Dependent LHGR Multipliers LHGRFAC(F) for Base Case or PROOS/PLUOOS (Loss of 'FULL' Feedwater Heating)1 (Reference
: 3) LHGRF 0.0 0.438 25.b 0.606 30.0 0.640 82.2 0.990 109.0 0.990 Table 5-11 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 22 of 26 Exelon Nuclear -Nuclear Fuels DOC ID: COLR Clinton 1 Rev. 14 CL 1C19 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 between 5.4 seconds and 6.6 seconds (References 6 and 11 ). 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. I Table 7-1 Reactor Power Limitation
-Turbine Bypass Valves Out of Service (References 2, 3, and 10) Turbine Bypass System Status I Maximum Reactor Thermal Power (% Rated} One Turbine Bypass Valve 100.0 Out of Service Two or More Turbine Bypass Valves 100.0 Out of Service Page 23 of 26 I Exelon Nuclear -Nuclear Fuels CL1C19 Core Operating Limits Report 8.0 Stability Protection Setpoints DOC ID: COLR Clinton 1 Rev. 14 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 Trip Setting 1.15. 16 Page 24 of 26 Exelon Nuclear -Nuclear Fuels DOC ID: COLR Clinton 1 Rev. 14 CL 1C19 Core Operating Limits Report 9.0 Modes of Operation The Allowed Modes of Operation with combinations of Equipment Out-of-Service (EOOS) are as described below in Table 9-1:
* EOOS Options 1 Base Case DL0 3.4 Base Case SL0 2*3 PROOS/PLUOOS DL0 3.4, 5 PROOS/PLUOOS SL0 2*3*5 Two or More TBVOOS DL0 4*6 Two or More TBVOOS SL0 2*6 Notes: Table 9-1 Modes of Operation (Reference
: 3) Operating Region Standard MELLLA ICF Yes Yes Yes Yes No No Yes Yes Yes Yes No No Yes Yes Yes Yes No No FFWTR 2 Coastdown Yes Yes No Yes Yes Yes No Yes Yes Yes No Yes 1. A single Main Steam Isolation Valve (MSIV) *out of service is supported at or below 75% power. (Reference
: 3) 2. Concurrent operation with SLO and Loss of 'FULL' Feedwater Heating (a change in temperature greater than 1 O &deg;F, but less than or equal to 50 &deg;F FWTR), MELLLA, ICF, or FFWTR has not been evaluated and thus is not a valid operating mode .. (Reference
: 8) 3. Includes 2 SRVOOS, 1 TCV stuck closed, 1 TSV stuck closed, 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. (Reference
: 12) 4. For operation with Loss of 'FULL' Feedwater Heating (a change in temperature greater than 10 &deg;F, but less than or equal to 50 &deg;F FWTR), the MAPLHGR is determined using the multiplier in Table 3-3 and the LHGR value is determined from Tables 5-8, 5-9, 5-10, and 5-11. 5. Concurrent operation with either or both of PROOS + PLUOOS is allowed. 6. Includes 2 SRVOOS 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. (Reference
: 12) 7. End-of-cycle power coastdown operation down to 40% reactor power is supported by Methodology Reference
: 1. Coastdown operation beyond the EOR condition is conservatively bounded by the reload licensing analyses at the EOR condition for a normal coastdown power profile. During coastdown, operation at a power level above that which can be achieved (at all-rods 0 out with all cycle extension features utilized, e.g., ICF, FFWTR) with steady-state equilibrium xenon concentrations is not supported. (Reference
: 3) Page25 of 26 Exelon Nuclear -Nuclear Fuels DOC ID: COLR Clinton 1 Rev. 14 CL 1C19 Core Operating Limits Report 10.0 Methodology The analytical methods used to determine the core operating limits shall be those previously reviewed and approved by the NRG, specifically those described in the following document:
: 1. Global Nuclear Fuel Document, "General Electric Standard Application for Reactor Fuel (GESTAR II)", NEDE-24011-P-A-26, January 2018 and U.S. Supplement NEDE-24011-P-A-26-US, January 2018. 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, 004N9724 Revision 0, "Supplemental Reload Licensing Report for Clinton Unit 1 Reload 18 Cycle 19,"September 2018.
* 4. Global Nuclear Fuel Document, 004N2113 Revision 0, "Fuel Bundle Information Report for Clinton Unit 1 Reload 18 Cycle 19," March.2018.
: 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 ES1700024 Revision 1, "Final Resolved OPL-3 Parameters for Clinton Unit 1 Cycle 19," January 16, 2018. 7. GE Hitachi Nuclear Energy Letter, CFL-EXN-LH1-12-059, "Affirmation of the Clinton Power Station Unit 1 MAPLHGR Reduction for Feedwater Riser Flow Asymmetry," April 25, 2012. 8. General Electric Document, GE-NE-0000-0026-1857-R1 Revision 1, "Evaluation of Operation With Equipment Out Of Service for the Clinton Power Station," June 28, 2004. 9. Global Nuclear Fuel Document, NEDC-33270P, Rev. 9, "GNF2 Advantage Generic co*mpliance with NEDE-24011-P-A (GESTAR II)," December 2017. 10. GE Hitachi Nuclear Energy Report, 003N4558-RO, "Removal of TBSOOS Power Restriction for Clinton," March 10, 2016. 11. General Electric Document, 22A3167, Rev. 6, "Neutron Monitoring System-Solid State Safety Option," December 22, 1988. 12. Exelon Transmittal of Design Information, TOOi NF173316 Revision 0, "Clinton Unit 1 Cycle 19 Customer Approved FRED Form," October 9, 2017. Page 26 of 26}}

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