U-604353, Submittal of the Core Operating Limits Report Cycle 18, Revision 12

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Submittal of the Core Operating Limits Report Cycle 18, Revision 12
ML17173A104
Person / Time
Site: Clinton Constellation icon.png
Issue date: 06/16/2017
From: Stoner T
Exelon Generation Co
To:
Document Control Desk, Office of Nuclear Reactor Regulation
References
U-604353
Download: ML17173A104 (29)
v • d • e


Text

~:v Exelon Generation 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

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 CL1C18 Core Operating Limits Report CORE OPERATING LIMITS REPORT FOR CLINTON POWER STATION UNIT 1CYCLE18 Prepared By: Date: s1a12017 Dale M. Bradish Reviewed By: QH/4 _f) Date: 5-<J-I :1 RE Reviewer - Robble7Heugel Reviewed By:

ESA R~' /dcris~key Date: 5/8/2017 Reviewed By: Date: 5/8/2017 Approved By:

Stat~on Qualified ca~

Reviewer By: Date: s-A /iz Page 1of27

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 DOC ID: COLR Clinton 1 Rev.12 CL 1C18 Core Operating Limits Report Revision History Revision Description Rev. 11 First issuance for Cycle 17 Rev. 12 First issuance for Cycle 18 Page 3 of 27

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 CL1C18 Core Operating Limits Report 1.0 Terms and Definitions AFTO Asymmetric Feedwater Temperature Operation Base Case 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 3).

Coastdown The reac~or 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 Dual Reactor Recirculation Loop Operation EOOS Equipment Out of Service FWfR Feedwater Temperature Reduction, including FFWfR or feedwater heater OOS FFWfR Final Feedwater Temperature Reduction FWHOOS Feedwater Heaters Out of Service ICF Increased Core Flow LHGR Linear Heat Generation Rate LHGRFAC(F) LHGR thermal limit flow dependent multipliers LHGRFAC(P) LHGR thermal limit power dependent multipliers Loss of 'FULL' 'FULL' Feedwater heating is temperature within +/-.10 °F of design NORMAL Feedwater temperature. The Loss of 'FULL' Feedwater Heating constitutes a change in Heating 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.

MAPLHGR Maximum Average Planar Linear Heat Generation Rate MCPR Minimum Critical Power Ratio MCPR(F) MCPR thermal limit flow dependent adjustments and multipliers MCPR(P) MCPR thermal limit power dependent adjustments and multipliers Page 6 of 27

Exelon Nuclear - Nuclear Fuels DOC ID: COLR Clinton 1 Rev.12 CL 1C18 Core Operating Limits Report MELLLA Maximum Extended Load Line Limit Analysis MSIV Main Steam Isolation Valve OLMCPR Operating Limit Minimum Critical Power Ratio oos Out of Service OPRM Oscillation Power Range Monitor PBDA Period Based Detection Algorithm PLUOOS Power Load Unbalance Out of Service PROOS Pressure Regulator Out of Service SLO Single Reactor Recirculation Loop Operation SRVOOS Safety Relief Valve Out of Service TBVOOS Turbine Bypass Valve(s) Out of Service - valves are not credited for fast opening or for normal pressure control TBSOOS Turbine Bypass System Out of Service TCV Turbine Control Valve TSV 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°F during cycle extension operation

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 1O °F, but less than or equal to 50 °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 Exposure 1 (Reference 3)

Avg. Planar Exposure MAPLHGR Limit (GWd/ST) (kW/ft) 0.00 13.78 17.15 13.78 60.78 6.87 63.50 5.50 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 CL1C18 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 1

Base Case SLO 1.42 1.33 PROOS/PLUOOS 1.39 1.36 DLO PROOS/PLUOOS 1.42 1.39 SL0 1 Two or More 1.45 1.35 TBVOOS DLO Two or More 1 1.48 1.38 TBVOOS SL0 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 1 2 Power Dependent MCPR Limits MCPR(P) and Multipliers K(P) for Base Case and Two or More TBVOOS *

(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 ~50 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 ~50 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 ~50 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.

1 2 Power Dependent MCPR Limits MCPR(P) and Multipliers K(P) for PROOS/PLUOOS *

(Reference 3)

Core Core Thermal Power (%)

EOOS Flow (% 0.0 21.6 <33.3 ?_33.3 43.3 60 ~85.0 >85.0 100.0 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 1.000 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 1.000 Option A/B > 50 2.49 2.49 2.20 Notes for Table 4-3:

1. Values are interpolated between relevant power levels.
2. Allowable EOOS conditions are listed in Section 9.0.

Page 15 of 27

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 CL1C18 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 Table 4-7 Single Loop Operation (SLO) Flow Dependent MCPR Limits MCPR(F) for Two or More TBVOOS 1 (Reference 3)

Core Flow MCPR(F)

(%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 1O °F, but less than or equal to 50 °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 U0 2 Rods 1 (References 4 and 9)

Fuel Type LHGR Limit See Table B-1 of GNF2 Reference 9 Table 5-2 Linear Heat Generation Rate Limits for Gad Rods 1 (References 4 and 9)

Fuel Type LHGR Limit See Table B-2 of GNF2 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 CL1C18 Core Operating Limits Report Table 5-3 Power Dependent LHGR Multipliers LHGRFAC(P) 1 (Reference 3)

Core Thermal Power (%)

Core EOOS Flow 0.0 21.6 <33.3 ~33.3 40.0 43.3 <60.0 ~60.0 <85.0 ~85.0 100.0 Combination (%of Rated)

LHGRFAC P)

~50 0.634 0.634 0.689 Base Case DLO/SLO 0.651 - 0.684 - - - - 1.000

> 50 0.572 0.572 0.600

~50 0.560 0.560 0.560 PROOS/PLUOOS DLO/SLO 0.560 0.560 - 0.709 0.749 0.868 0.906 1.000

> 50 0.560 0.560 0.560 Two or More ~50 0.634 0.634 0.689 TBVOOS 0.651 - 0.684 - - - - 1.000 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

Exelon Nuclear - Nuclear Fuels DOC ID: COLR Clinton 1Rev.12 CL1C18 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 TBVOOS 1 (Reference 3)

Core Flow LHGRFAC(F)

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

LHGR Fuel SLO Type Multi lier All Fuel Types 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 Table 5-7 Power Dependent LHGR Multipliers LHGRFAC(P)

(Loss of 'FULL' Feedwater Heating) 1 '2 (Reference 3)

Core Thermal Power (%)

Core EOOS Flow 0.0 21.6 <33.3  ?,33.3 40.0 43.3 <60.0 ?,60.0 <85.0 ?,85.0 100.0 Combination (%of Rated)

LHGRFAC P)

~50 0.628 0.628 0.682 Base Case DLO 0.644 - 0.677 - - - - 0.990

> 50 0.566 0.566 0.594

~50 0.554 0.554 0.554 PROOS/PLUOOS 0.554 0.554 - 0.702 0.742 0.859 0.897 0.990 DLO

> 50 0.554 0.554 0.554

~50 0.628 0.628 0.682 Two or More TBVOOS DLO 0.644 - 0.677 - - - - 0.990

> 50 0.566 0.566 0.594 Notes for Table 5-7:

1. Linear interpolation should be used for points not listed in the table.
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 CL1C18 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 LHGRF.:.~\i". 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)

Corresponding Maximum Confirmation PBDA Trip Amplitude Count Trip Setting 1.12 14 Page 25 of 27

Exelon Nucle ar - Nuclear Fuels DOC ID: COLR Clinton 1 Rev. 12 CL 1C18 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 bel ow in Table 9-1:

Table 9-1 Modes of Operation (Refer~nce 3)

Operating Region 2 1 EOO S Options Standard MELLLA ICF FFWTR Coastdown 3

Base Case DL0 Yes Yes Yes Yes Yes 3

Base Case SL0 1' Yes No No No Yes 3

PROOS/P LUOOS DL0 '5 Yes Yes Yes Yes Yes 35 PROOS/P LUOOS SL0 1 ' ' Yes No No No Yes Two or More TBVOOS DL04 Yes Yes Yes Yes Yes Two or More TBVOOS SL0 1*4 Yes No No No Yes Notes:

1. Concurrent operation with SLO and Loss of 'FULL' Feedwater Heating (a change in temperature greater than 10 °F, but less than or equal to 50 °F FWfR), MELLLA, ICF, or FFWfR has not been evaluated and thus is not a valid operating mode. (Reference 8)
2. A single Ma in 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 closed, 1 TBVOOS, and up to a 50°F feedwater temperature reduction (FWfR includes feedwater heater OOS or final feedwater temperature reduction) at any point in cycle operation in Dual Loo p mode.
4. Includes 2 SRVOOS and up to a 50°F feedwater temperature reduction (FWfR includes feedwater heater OOS or final feedwater t emperature 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

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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