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{{Adams
#REDIRECT [[U-604353, Submittal of the Core Operating Limits Report Cycle 18, Revision 12]]
| number = ML17173A104
| issue date = 06/16/2017
| title = Clinton, Unit 1, Submittal of the Core Operating Limits Report Cycle 18, Revision 12
| 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-604353
| document type = Fuel Cycle Reload Report, Letter
| page count = 29
}}
 
=Text=
{{#Wiki_filter:Clinton Power Station 8401 Power Road Clinton, IL 61727 U-604353 June 16, 2017 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 Exelon Generation
 
==Subject:==
 
Submittal of the Core Operating Limits Report for Clinton Power Station, Unit 1, Cycle 18, Revision 12 In accordance with Technical Specification 5.6.5, Core Operating Limits Report (COLR), Item d., Exelon Generation Company (EGC), LLC is submitting Revision 12 of the COLR for Clinton Power Station, Unit 1, Cycle 18. 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 KP/cac
 
==Attachment:==
 
Core Operating Limits Report for Clinton Power Station Unit 1, Cycle 18, Revision 12 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 18, Revision 12 Exelon Nuclear*
Nuclear Fuels DOC ID: COLR Clinton 1 Rev.12 CL 1C18 Core Operating Limits Report CORE OPERA TING LIMITS REPORT FOR CLINTON POWER STATION UNIT 1CYCLE18 Prepared By: Dale M. Bradish Reviewed By: QH/4 _f) RE Reviewer
-Robble7Heugel Reviewed By: ESA Reviewed By: Approved By:
Qualified Reviewer By: Page 1of27 Date: s1a12017 Date: 5-<J-I :1 Date: 5/8/2017 Date: 5/8/2017 Date: s-A /iz Exelon Nuclear -Nuclear Fuels DOC ID: COLR Clinton 1 Rev.12 CL 1C18 Core Operating Limits Report Table of Contents 0.0 Revision History 3 1.0 Terms and Definitions 6 2.0 General Information 8 3.0 MAPLHGR Limits 9 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 CL 1C18 Core Operating Limits Report Revision Rev. 11 Rev. 12 DOC ID: COLR Clinton 1 Rev.12 Revision History Page 3 of 27 Description First issuance for Cycle 17 First issuance for Cycle 18 Exelon Nuclear -Nuclear Fuels DOC ID: COLR Clinton 1Rev.12 CL 1C18 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 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 Table 4-4 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 Table 4-7 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) Multiplier 21 Page 4 of 27 Exelon Nuclear -Nuclear Fuels DOC ID: COLR Clinton 1 Rev. 12 CL 1C18 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 Multipliers 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 DOC ID: COLR Clinton 1 Rev. 12 CL 1C18 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&deg;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 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&deg;F at rated power. Temperature DLO EOOS FWfR FFWfR FWHOOS ICF LHGR LHGRFAC(F)
LHGRFAC(P)
Loss of 'FULL' Feedwater Heating MAPLHGR MCPR MCPR(F) MCPR(P) 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 Linear Heat Generation Rate LHGR thermal limit flow dependent multipliers LHGR thermal limit power dependent multipliers
'FULL' Feedwater heating is temperature within +/-.10 &deg;F of design NORMAL temperature.
The Loss of 'FULL' Feedwater Heating constitutes a change in temperature greater than 10 &deg;F, but less than or equal to 50 &deg;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 MCPR thermal limit power dependent adjustments and multipliers Page 6 of 27 Exelon Nuclear -Nuclear Fuels DOC ID: COLR Clinton 1 Rev.12 CL 1C18 Core Operating Limits Report MELLLA MSIV OLMCPR oos OPRM PBDA PLUOOS PROOS SLO SRVOOS TBVOOS TBSOOS TCV TSV 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 27 Exelon Nuclear -Nuclear Fuels DOC ID: COLR Clinton 1 Rev. 12 CL 1C18 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 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 (ICF) up to 107% of rated core flow
* Final Feedwater Temperature Reduction (FFWTR) up to 50&deg;F during cycle extension operation
* Feedwater Heater Out of Service (FWHOOS) up to 50&deg;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 ID: COLR Clinton 1 Rev.12 CL 1C18 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 (a change in temperature greater than 1 O &deg;F, but less than or equal to 50 &deg;F FWTR), 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 DOC ID: COLR Clinton 1 Rev. 12 CL 1C18 Core Operating Limits Report Table 3-2 MAPLHGR Single Loop Operation (SLO) Multiplier (Reference
: 3) Fuel MAPLHGR Type SLO Multiplier All Fuel Types 0.760 Table 3-3 MAPLHGR Multiplier for Loss of 'FULL' Feedwater Heating (Reference
: 7) Fuel MAPLHGR Type Multiplier All Fuel Types 0.990 Page 10 of 27 Exelon Nuclear -Nuclear Fuels DOC ID: COLR Clinton 1 Rev.12 CL 1C18 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 of flow based on the applicable plant condition.
The limits for dual loop operation are listed in Tables 4-4 and 4-6. The limits for single loop operation are listed in Tables 4-5 and 4-7. The MCPR(F) determined from these tables is the flow dependent OLMCPR. 4.1.2 Automatic Flow Control MCPR Limits Automatic Flow Control MCPR Limits are not provided.
Page 11of27 Exelon Nuclear -Nuclear Fuels DOC ID: COLR Clinton 1 Rev. 12 CL 1C18 Core Operating Limits Report 4.1.3 Option A and Option B Option A and Option B refer to use of scram speeds for establishing MCPR operating limits. Option A scram speed is the BWR/6 Technical Specification scram speed. The Technical Specification scram speeds must be met to utilize the Option A MCPR limits. 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 less 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. 12 CL 1C18 Core Operating Limits Report Table 4-1 Operating Limit Minimum Critical Power Ratio (Reference
: 3) EOOS Option A Option B Combination All Exposures All Exposures Base Case DLO 1.39 1.30 Base Case SLO 1 1.42 1.33 PROOS/PLUOOS 1.39 1.36 DLO PROOS/PLUOOS 1.42 1.39 SL01 Two or More 1.45 1.35 TBVOOS DLO Two or More 1.48 1.38 TBVOOS SL01 Notes for Table 4-1: 1. SLO Option A(B) OLMCPR is the transient DLO Option A(B) OLMCPR plus 0.03. Page 13 of 27 Exelon Nuclear -Nuclear Fuels DOC ID: COLR Clinton 1 Rev. 12 CL 1C18 Core Operating Limits Report Table 4-2 Power Dependent MCPR Limits MCPR(P) and Multipliers K(P) for Base Case and Two or More TBVOOS1* 2 (Reference
: 3) Core Core Thermal Power(%)
EOOS Flow (% 0.0 21.6 <33.3 >33.3 <43.3 >43.3 .'.5,70.0
>70.0 100.0 Combination of Rated) MCPR(P) K(P) Base Case 50 2.31 2.31 2.10 DLO 1.617 1.590 1.313 1.212 1.163 1.000 Option NB > 50 2.46 2.46 2.17 Base Case 2.34 2.34 2.13 SLO 1.617 1.590 1.313 1.212 1.163 1.000 Option NB > 50 2.49 2.49 2.20 Two or More 2.31 2.31 2.10 TBVOOS DLO 1.617 1.590 1.329 1.212 1.163 1.000 Option NB > 50 2.46 2.46 2.17 Two or More 2.34 2.34 2.13 TBVOOS SLO 1.617 1.590 1.329 1.212 1.163 1.000 Option NB > 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 Exelon Nuclear -Nuclear Fuels DOC ID: COLR Clinton 1 Rev.12 CL 1C18 Core Operating Limits Report Table 4-3. Power Dependent MCPR Limits MCPR(P) and Multipliers K(P) for PROOS/PLUOOS 1* 2 (Reference
: 3) Core Core Thermal Power (%) EOOS Flow (% 0.0 21.6 <33.3 ?_33.3 43.3 60
>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 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 Fuels DOC ID: COLR Clinton 1 Rev.12 CL 1C18 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 16 of 27 Exelon Nuclear -Nuclear Fuels DOC ID: COLR Clinton 1 Rev. 12 CL 1C18 Core Operating Limits Report Table 4-6 Dual Loop Operation (DLO) 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 of 27 Exelon Nuclear -Nuclear Fuels DOC ID: COLR Clinton 1 Rev.12 CL 1C18 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:==
 
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 Multiplier, LHGRFAC(P),
the flow dependent LHGR Multiplier, LHGRFAC(F),
or the single loop operation (SLO) Multiplier 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 multiplier 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 (a change in temperature greater than 1 O &deg;F, but less than or equal to 50 &deg;F FWTR), 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. 12 CL 1C18 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 1 Linear interpolation should be used for points not listed in the table. Page 19 of 27 Exelon Nuclear -Nuclear Fuels DOC ID: COLR Clinton 1 Rev.12 CL 1C18 Core Operating Limits Report Core Table 5-3 Power Dependent LHGR Multipliers LHGRFAC(P) 1 (Reference
: 3) Core Thermal Power (%) EOOS Flow 0.0 21.6 <33.3 40.0 43.3 <60.0 Combination
(%of Rated) LHGRFAC P) Base Case 0.634 0.634 0.689 DLO/SLO 0.651 -0.684 --> 50 0.572 0.572 0.600 PROOS/PLUOOS 0.560 0.560 0.560 DLO/SLO 0.560 0.560 -0.709 0.749 > 50 0.560 0.560 0.560 Two or More 0.634 0.634 0.689 TBVOOS 0.651 -0.684 --DLO/SLO > 50 0.572 0.572 0.600 Notes for Table 5-3: 1. Linear interpolation should be used for points not listed in the table. Page 20 of 27 <85.0 --0.868 0.906 --100.0 1.000 1.000 1.000 Exelon Nuclear -Nuclear Fuels DOC ID: COLR Clinton 1Rev.12 CL 1C18 Core Operating Limits Report Table 5-4 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 5-5 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) Multiplier (Reference
: 3) Fuel Type All Fuel Types LHGR SLO Multi lier 0.760 1 Linear interpolation should be used for points not listed in the table. Page 21of27 Exelon Nuclear -Nuclear Fuels DOC ID: COLR Clinton 1 Rev.12 CL 1C18 Core Operating Limits Report Core EOOS Flow Combination
(%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 (%) 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. ?,60.0 <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). Page 22 of 27 Exelon Nuclear -Nuclear Fuels DOC ID: COLR Clinton 1 Rev.12 CL 1C18 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 1 (%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.12 CL 1C18 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. Table 7-1 Reactor Power Limitation
-Turbine Bypass Valves Out of Service (References 2, 3, and 10) Turbine Bypass System Status 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 24 of 27 Exelon Nuclear -Nuclear Fuels DOC ID: COLR Clinton 1 Rev. 12 CL 1C18 Core Operating Limits Report 8.0 Stability Protection Setpoints 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 1.12 14 Page 25 of 27 Exelon Nucle ar -Nuclear Fuels Operating Limits Report DOC ID: COLR Clinton 1 Rev. 12 CL 1C18 Core 9.0 Mode s of Operation The Allowed Modes of Operation with combinations of Equipment Out-of-Service (EOOS) are as ow in Table 9-1: described bel EOO S Options2 Base Case DL03 Base Case SL01'3 PROOS/P LUOOS DL03'5 PROOS/P LUOOS SL01'3'5 Two or Mor e TBVOOS DL04 Two or Mor e TBVOOS SL01*4 Table 9-1 Modes of Operation
: 3) Operating Region Standard MELLLA ICF Yes Yes Yes Yes No No Yes Yes Yes Yes No No Yes Yes Yes Yes No No FFWTR1 Coastdown Yes Yes No Yes Yes Yes No Yes Yes Yes No Yes Notes: 1. 2. 3. 4. 5. Concurrent operation with SLO and Loss of 'FULL' Feedwater Heating (a change in temperature greater than 10 &deg;F, but equal to 50 &deg;F FWfR), MELLLA, ICF, or FFWfR has not been evaluated and thus is not a valid operating erence 8) less than or mode. (Ref A single Ma in Steam Isolation Valve (MSIV) out of service is supported at or below 75% power. (Reference
: 3) Includes 2 reduction
( SRVOOS, 1 TCV stuck closed, 1 TSV stuck closed, 1 TBVOOS, and up to a 50&deg;F feedwater temperature FWfR includes feedwater heater OOS or final feedwater temperature reduction) at any point in cycle operation p mode. in Dual Loo Includes 2 SRVOOS and up to a 50&deg;F feedwater temperature reduction (FWfR includes feedwater heater OOS or final emperature reduction) at any point in cycle operation in Dual Loop mode. feedwater t Concurrent operation with either or both of PROOS + PLUOOS is allowed.
Page 26 of 27 Exelon Nuclear -Nuclear Fuels DOC ID: COLR Clinton 1 Rev.12 CL 1C18 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 NRC, specifically those described in the following documents:
: 1. Global Nuclear Fuel Document, "General Electric Standard Application for Reactor Fuel (GESTAR II)", NEDE-24011-P-A-24, March 2017 and U.S. Supplement NEDE-24011-P-A-24-US, March 2017. 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, 004N1512 Revision 0, "Clinton Unit 1 Cycle 18 Reload Licensing Reports -Supplemental Reload Licensing Report (SRLR)",
April 2017. 4. Global Nuclear Fuel Document, 004N1943 Revision 0, "Clinton Unit 1 Cycle 18 Reload Licensing Reports -Fuel Bundle Information Report (FBIR)",
April 2017. 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 ES1700003 Revision 1, "Clinton Unit 1 Cycle 18 Final Resolved OPL-3 Parameters",
March 13, 2017. 7. GE Hitachi Nuclear Energy Letter, CFL-EXN-LH 1-12-059, "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. 7, "GNF2 Advantage Generic Compliance with NEDE-24011-P-A (GESTAR II)", October 2016. 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. Page 27 of 27}}

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