U-604219, Submittal of the Core Operating Limits Report, Cycle 16, Revision 10

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Submittal of the Core Operating Limits Report, Cycle 16, Revision 10
ML15159A191
Person / Time
Site: Clinton Constellation icon.png
Issue date: 06/03/2015
From: Newcomer M
Exelon Generation Co
To:
Document Control Desk, Office of Nuclear Reactor Regulation
References
U-604219 COLR Clinton 1, Rev. 10
Download: ML15159A191 (28)
v • d • e


Text

AwExe!on Generation.

Clinton Power Station 8401 Power Road Clinton, IL 61727 U-604219 June 03, 2015 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 16, Revision 10 In accordance with Technical Specification 5.6.5, Core Operating Limits Report (COLR),

Item d., Exelon Generation Company (EGC), LLC is submitting Revision 10 of the COLR for Clinton Power Station, Unit 1, Cycle 16.

Should you have any questions concerning this report, please contact Mr. Jeffrey E.

Cunningham at (217) 937-2800.

Respectfully,

,a %ewcomer Site Vice President Clinton Power Station JLP/cas

Attachment:

Core Operating Limits Report for Clinton Power Station Unit 1, Cycle 16, Revision 10 cc: NRC Regional Administrator, Region III NRC Senior Resident Inspector - Clinton Power Station Accf

ATTACHMENT Core Operating Limits Report for Clinton Power Station Unit 1, Cycle 16, Revision 10

"-~- '

Exelon Nucesr- Nudear Fuels DOC ID: COLR Cntton I Rev. 10 CLICIS Caoe Operating limts Report

.4 CORE OPERATING UMIT$ REPORT FOR CLINTON POWER STATION UNIT I CYCLE 16 Prepared By. Date: 8/11/2015 Reviewed By:. Date: -

RE Re~m - Rabl SGieiga Reviewed By:.

E Reviewed By:- Date: ,,_.______

In(lependent Reviewer- Frank W. Trikur Approved By: Date: 5/12/15 HF Mdaer- James J. Tusr Station Qualified Reviewer By: _ Date:

Page I of 26

Exelon Nuclear - Nuclear Fuels DOC IDM COLR Clinton I Rev. 10-CLI C16 Core Operating Limits Report Table of Contents 1.0 Terms and Definitions 5 2.0 General Information 7 3.0 MAPLHGR Limits 8 4.0 MCPR Limits 10 5.0 Linear Heat Generation Rate Limits 17 6.0 Reactor Protection System (RPS) Instrumentation 23 7.0 Turbine Bypass System Parameters 23 8.0 Stability Protection Setpoints 24 9.0 Modes of Operation 25 10.0 Methodology 26 11.0 References 26 Page 2 of 26

Exelon Nuclear- Nuclear Fuels -. DOC ID: COLR Clinton I Rev. 10 -

CLIC16 Core Operating Limits Report List of Tables Page Table 3-1 MAPLHGR Versus Average Planar Exposure - GE14C 8 Table 3-2 MAPLHGR Versus Average Planar Exposure - GNF2 8 Table 3-3 MAPLHGR Single Loop Operation (SLO) Multiplier 9 Table 3-4 MAPLHGR Multiplier for Loss of 'FULL' Feedwater Heating 9 Table 4-1 Operating Limit Minimum Critical Power Ratio 12 Table 4-2 Power Dependent MCPR Limits MCPR(P) and Multipliers K(P) 13 Table 4-3 PROOS/PLUOOS/TCVFASOOS Power Dependent MCPR Limits 14 MCPR(P) and Multipliers K(P)

Table 4-4 Dual Loop Operation (DLO) Flow Dependent MCPR Limits MCPR(F) 15 for Base Case or PROOS/PLUOOS/TCVFASOOS Table 4-5 Single Loop Operation (SLO) Flow Dependent MCPR Limits MCPR(F) 15 for Base Case or PROOS/PLUOOS/TCVFASOOS 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 Power Dependent LHGR Multiplier LHGRFAC(P) 19 Table 5-4 Flow Dependent LHGR Multiplier LHGRFAC(F) for Base Case or 20 PROOSIPLUOOSITCVFASOOS Table 5-5 Flow Dependent LHGR Multiplier LHGRFAC(F) for Two or More TBVOOS 20 Table 5-6 LHGR Single Loop Operation (SLO) Reduction Factor 20 Page 3 of 26

Exelon Nuclear - Nuclear Fuels DOC ID: COLR Clinton I Rev.10 CLIC16 Core Operating Limits Report Table 5-7 Power Dependent LHGR Muftip!ier LHGRFAC(P) (Loss of 'FULL' 21 Feedwater Heating)

Table 5-8 Flow Dependent LHGR Multiplier LHGRFAC(F) for Base Case or 22 PROOS/PLUOOS/TCVFASOOS (Loss of 'FULL' Feedwater Ieating)

Table 5-9 Flow Dependent LHGR Multiplier 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 Setpoints 24 Table 9-1 Modes of Operation 25 Page 4 of 26

Exelon Nuclear - Nuclear Fuel ,I"- ' -. ., .. . DOC-ID: COLR Clinton I Rev. 10 ""

CLI C16 Core Operating Umits Report 1.0 Terms and Definitions ADSOOS Automatic Depressudzation System Valve Out of Service Base Case A case analyzed with two (2) Safety-Relief Valves Out-of-Service (OOS), one (1)

Automatic Depressurzation System valve 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 (FWTR includes feedwater heater OOS or final feedwater temperature reduction) at any point in the cycle operation in Dual Loop mode (Reference 3).

Coastdown The reactor condition where thermal power gradually decreases due to fuel depletion while the following conditions are met: 1) all operable control rods are fully withdrawn and 2) all cycle extension techniques have been exhausted including FFWTR and ICF.

DLO Dual Reactor Recirculation Loop Operation FFWTR Final Feedwater Temperature Reduction FWHOOS Feedwater Heaters Out of Service ICF Increased Core Flow LHGR Linear Heat Generation Rate LHGRFAC(F) LHGR thermal limit flow dependent multipliers LHGRFAC(P) LHGR thermal limit power dependent multipliers 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 MELLLA Maximum Extended Load Line Limit Analysis MSIV Main Steam Isolation Valve OLMCPR Operating Limit Minimum Critical Power Ratio OPRM Oscillation Power Range Monitor PBDA Period Based Detection Algorithm Page 5 of 26

Exelon Nuclear - Nuclear Fuels DOC ID: COLR, Clinton 1Rev. 10 CLIC16 Core Operating Limits Report 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 TCV Turbine Control Valve TCVFASOOS Turbine Control Valve Fast Acting Solenoid Out of Service TSV Turbine Stop Valve Page 6 of 26

Exelbn Nuclear- Nuclear Fuels--*.. DOC ID: COLR.Clintonl Rev. 10-.

CLIC16 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 Umit down to 99% of rated core flow during full power operation
  • Increased Core Flow (ICF) up to 107% of rated core flow

any time during the cycle prior to cycle extension.

Equipment out of service conditions are as defined in Section 1 and Section 9.

Page 7 of 26

Exelon Nuclear - Nuclear Fuels DOC ID: COLR Clinton I Rev. 10-CLICI1 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 for GE14C fuel. Table 3-2 is used to determine the maximum average planar linear heat generation rate (MAPLHGR) limit for GNF2 fuel. Limits listed in Table 3-1 and Table 3-2 are for dual reactor recirculation loop operation (DLO).

For single reactor recirculation loop operation (SLO), the MAPLHGR limits given in Table 3-1 and Table 3-2 must be multiplied by a SLO MAPLHGR multiplier provided in Table 3-3.

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 and 3-2 must be multiplied by a LHGR multiplier provided in Table 3-4. This multiplier accounts for potential feedwater riser flow asymmetries (Reference 7).

Table 3-1 MAPLHGR Versus Average Planar Exposure - GE14C 1 (Reference 3)

Avg. Planar Exposure MAPLHGR Limit (GWdIST) (kWlft) 0.00 12.82 19.13 12.82 57.61 8.00 63.50 5.00 Table 3-2 MAPLHGR Versus Average Planar Exposure - GNF21 (Reference 3)

Avg. Planar Exposure MAPLHGR Limit (GWdIST) (kW/ft) 0.00 13.78 17.15 13.78 60.78 6.87 63.50 5.50 Linear interpolation should be used for points not listed in the table.

Page 8 of 26

Exelon Nuclear -Nuclear Fuels - "-,

'-- -'-" *- DOC-ID: COLR'Cllnton I 'Rev. 10 -"

CLIC16 Core Operating Limits Report Table 3-3 MAPLHGR Single Loop Operation (SLO) Multiplier (Reference 3)

Fuel MAPLHGR Type SLO Multiplier All Fuel Types 0.760 Table 3-4 MAPLHGR Multiplier for Loss of 'FULL' Feedwater Heating (Reference 7)

Fuel MAPLHGR Type Multiplier All Fuel Types 0.990 Page 9 of 26

Exelon Nuclear - Nuclear Fuels DOC ID: COLR Clinton I Rev. 10 CLI C16 Core Operating Limits Report 4.0 MCPR Limits 4.0 Technical Specification Reftrence:

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 Qf 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 10 of 26

Exelon Nuclear - Nuclear Fuels ""- ................. DOC ID: COLR Clinton I Rev. 10 -

CLIC16 Core Operating Limits Report 4.1.3 Option A and Ortion B Option A and Option B refer to use of scram speeds for establishing MCPR operating limits.

Option A scram speed is the BWR/6 Technical Specification scram speed. The Technical Specification scram speeds must be met to utilize the Option A MCPR limits. Reload analyses performed by GNF for Cycle 16 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. Ifthe 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 Cycle 16 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 1t of 26

Exelon Nuclear - Nuclear Fuels "I DOC ID: COLR Clinton I Rev. 10 CLICI Core Operating Limits Report Table 4-1 Operating Limit Minimum Critical Power Ratio (References 3 and 11)

GNF2 Fuel GE14C Fuel GNF2 Fuel GE14C Fuel Combination Option A Option A Option B Option B All Exposures All Exposures All Exposures All Exposures Base Case DLO 1.40 1.35 1.30 1.30 Base Case SLO1 1.43 1.38 1.33 1.33 PROOS/PLUOOS/

TCVFSOOS 1.40 1.37 1.36 1.37 TCVFASOOS DLO PROOS/PLUOOS/

TCVFASOOS 1.43 1.40 1.39 1.40 SLO 1 Two or More 1.44 1.40 i.35 1.32 TBVOOS DLO Two or More TBVOOS SLO' 147 1.43 138 1.35 Notes for Table 4-1:

1. SLO Option A(B) OLMCPR is the transient DLO Option A(B) OLMCPR plus 0.03.

Page 12 of 26

Exelon Nuclear- Nuclear Fuels.........-"---' . . DOC ID:COLR Clinton I Rev. 10 CLIC16 Core Operating Limits Report Table 4-2 1 Power Dependent MCPR Limits MCPR(P) and Multipliers K(P) ' 2 (Reference 3)

Core Core Thermal Power (%)

EoOS Flow (% 0.0 T 2 1.6 <33.3 >33.3  :<43.3 >43.31 <70.0 >70.0 100.0 Combination of Rated) MCPR(P) K(P)

Base Case < 50 2.31 2.31 2.10 DLO NF2GE4 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 N 1.617 1.590 1.313 1.212 1.163 1.000 GNF2/GEI4C Option A/B > 50 2.49 2.49 2.20 Two or More < 50 2.31 2.31 2.10 TBVOOS DLO 1.617 1.590 1.313 1.212 1.163 1.000 GNF2IGE14C 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 1.313 1.212 1.163 1.000 GNF2AGE94C Option A/B I> 50 12.49 12.49 "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 13 of 26

Exelon Nuclear - Nuclear Fuels DOC ID: COLRClinton I Rev. 10-CLI C16 Core Operating Limits Report Table 4-3 PROOSIPLUOOSITCVFASOOS Power Dependent MCPR Limits MCPR(P) and Multipliers K(P)' 2 (Reference 3)

Core Core Thermal Power (%)

EOOS o o Flow (% 0. 21.6 <33.3 33.3 43.3 60 185.0 85.0 100.0 of Rated) MCPR(P) K(P)

PROOS/PLUOOS/ < 50 2.31 2.31 2.10 TCVFASOOS DLO 1.617 1.590 1.436 1.309 1.090 1.000 GNF2/GE14C Option A/B > 50 2.46 2.46 2.17 PROOSIPLUOOSI < 50 2.34 2.34 2.13 TCVFASOOS SLO 1.617 1.590 1436 1309 1.090 1.000 GNF2/GE14C 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 14 of 26

Exelon Nuclear "Nuclear Fuels I....' .'.... DOC ID: COLR Clinton I Rev. 10 I CLI C16 Core Operating Limits Report Table 4-4 Dual Loop Operation (OLO) Flow Dependent MCPR Limits MCPR(F) for Base Case or PROOSIPLUOOSITCVFASOOS 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 PROOSIPLUOOSITCVFASOOS 1 (Reference 3)

Core Flow MCPR(F)

(% rated) 0.0 1.91 25.0 1.73 84.1 1.30 109.0 1.30

'Linear interpolation should be used for points not listed in the table.

Page 15 of 26

Exelon Nuclear - Nuclear Fuels DOC ID: COLR Clinton I Rev. 10 CLI C16 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 16 of 26

. Exelon Nuclear-'Nuclear Fuels. -' ................... ... DOCID:'COLR Clinton-1,Rev.10* ..

CLI CI 6 Core Operating Limits Report 6.0 Linear Heat Generation Rate Limits 5.1 Technical Specification

Reference:

Section 3.2.3, 3.4.1, and 3.7.6.

5.2

Description:

The linear heat generation rate (LHGR) limit is the product of the exposure dependent LHGR limit (from Table 5-1 for U02 fuel rods and Table 5-2 for Gadolinia fuel rods) and the minimum of: the power dependent LHGR Factor, LHGRFAC(P), the flow dependent LHGR Factor, LHGRFAC(F), or the single loop operation (SLO) multiplication factor ifapplicable. 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 (+10 OF outside design NORMAL temperature, meaning changes in feedwater temperature greater than 10 OF and less than or equal to 50 OF), 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 17 of 26

Exelon Nuclear- Nuclear Fuels ' DOC ID. COLRClinton I Rev. 10 CLICI6 Core Operating Limits Report Table 5-1 Linear Heat Generation Rate Limits for U0 2 Rods' (References 4, 9. and 10)

FuelType i LHGR Limit I NF2 See Table B-1 of Reference 9 SGE14C See Table D-2 of j Reference 10 Table 5-2 Linear Heat Generation Rate Limits for Gad Rods' (References 4, 9, and 10)

Fuel Type IfLHGR Limit GN2 jSee Table B-2 of Reference 9 GE4 1 See Table D-4 of Reference 10 1 Linear interpolation should be used for points not listed in the table.

Page 18 of 26

q*'9 - . Exelon Nuclear - Nuclear Fuels' '-.. - -....-...-.

. DOC ID: COL;R-Clinton I Rev.,10 ....

CLICI6 Core Operating Limits Report Table 5-3 Power Dependent LHGR Multiplier LHGRFAC(P)1 (Reference 3)

Core - -Core Thermal Power (%M EQOS 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 I Rated)

I I -

LHGRFAC P)

Base Case < 50 0.634 0.634 0.689

-L/SO0.651 - 0.684 - - - - 1.000 DIQISLO > 50 0.572 0.572 0.600 PROOS/PLUOOSI <50 0.560 0.560 0.560 TCVFASOOS 0.560 0.560 - 0.709 0.749 0.868 0.906 1.000 DLO/SLO >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

- --- I- - -- --

Notes for Table 5-3:

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 I Rev.10-CLIC16 Core Operating Limits Report Table 5-4 Flow Dependent LHGR Multiplier LHGRFAC(F) for Base Case or PROOSIPLUOOSITCVFASOOS, (Reference 3)

Core Flow LHGRFAC(F)

(%rated) LGRC(F 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 Multiplier LHGRFAC(F) for Two or More TBVOOS1 (Reference 3)

Core Flow LHGRFAC(F)

(% rated) __GRAC(F 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)

FuelType LHGR SLO Type Multiplier All Fuel Types 0.760 Linear interpolation should be used for points not listed in the table.

Page 20 of 26

Exelon Nuclear- Nuclear FuIB . . '.::, DOC ID: COLRGlinton I Rev. 10 , .

CLI C16 Core Operating Limits Report Table 5-7 Power Dependent LHGR Multiplier LHGRFAC(P)

(Loss of 'FULL' Feedwater Heating)"'

(Reference 3)

____Core Thermal Power (%M Core EQOS 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 I I I I I I- I Rated) - LP),- I LHGRFA

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

> 50 0.566 0.566 0.594 PROOS/PLUOOS/ <50 0.554 0.554 0.554 TCVFASOOS 0.554 0.554 - 0.702 0.742 0.859 0.897 0.990 DLO > 50 0.554 0.554 0.554 Two or More < 50 0.628 0.628 0.682 0.644 - 0.677 - - - - 0.990 TBVOOS DLO > 50 0.566 0.568 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 21 of 26

Exelon Nuclear - Nuclear Fuels. DOC ID: COLR Clinton I Rev. 10 CLI C16 Core Operating Limits Report Table 5-8 Flow Dependent LHGR Multiplier LHGRFAC(F) for Base Case or PROOSIPLUOOS/TCVFASOOS (Loss of 'FULL' Feedwater Heating)1 (Reference 3)

Core Flow LHGRFAC(F)

(% rated) __GRC(F 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 Multiplier LHGRFAC(F) for Two or More TBVOOS (Loss of 'FULL' Feedwater Heating)1 (Reference 3)

Core Flow LHGRFAC(F)

(%rated) LHGFA(F 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

'Linear interpolation should be used for points not listed in the table.

Page 22 of 26

Exelon Nuclear -Nuclear Fuels...................... DOC ID: COLR Clinton I Rev. 10-'

CLICi6 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 (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 3.7.6 action statement A.1. 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 12)

Turbine Bypass System Status Maximum Reactor Thermal Power (% Rated)

One Turbine Bypass Valve 100.0 Out of Service 1 Two or More Turbine Bypass Valves 90.0 Out of Service Page 23 of 26

Exelon Nuclear - Nuclear Fuels DOC ID: COLR Clinton I Rev. 10 CLIC16 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 Setpoints for the OPRM System for use in Technical Specification 3.3.1.3 are found in Table 8-1. These values are based on the cycle specific analysis documented in Reference 3.

Stability-based OLMCPR is non-limiting for either PBDA setpoint in Table 8-1. The higher PBDA setpoint provides greater margin to spurious scram.

Table 8-1 OPRM PBDA Trip Setpoints (Valid for All Conditions)

(Reference 3)

Page 24 of 26

Exelon Nuclear --Nuclear Fuels DOC ID: COLR Clinton I Rev. 10.

CLICI6 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:

Table 9-1 Modes of Operation (Reference 3)

Operating Region EOOS Options 2 Standard MELLLA ICF FFWTR1 Coastdown Base Case DLO 3 Yes Yes Yes Yes Yes Base Case SLO' 3 Yes No No No Yes PROOS/PLUOOS/3 TCVFASOOS DLO .5 Yes Yes Yes Yes Yes PROOS/PLUOOSI TCVFASOOS SLO1' 3.5 Yes No No No Yes Two or More TBVOOS DLO4 Yes Yes Yes Yes Yes Two or More TBVOOS SLO". Yes No No No Yes Notes:

1. Concurrent operation with SLO and Loss of FULL Feedwater Heating (+/-10 *Foutside design NORMAL temperature, meaning changes in feedwater temperature greater than 10 'F and less than or equal to 50 "F). MELLLA, ICF, or FFWTR has not been evaluated and thus is not a valid operating mode. (Reference 8)
2. Asingle Main Steam Isolation Valve (MSIV) out of service is supported at or below 75% power. (Reference 3)
3. Includes 2 SRVOOS, I ADSOOS, 1 TCV stuck closed, I TSV stuck closed, 1 TBVOOS, and up to a 50°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, 1 ADSOOS, and up to a 50°F feedwater temperature reduction (FWTR Includes feedwater heater OOS or final feedwater temperature reduction) at any point in cycle operation in Dual Loop mode.
5. Concurrent operation with any or all of PROOS + PLUOOS + TCVFASOOS is allowed.

Page 25 of 26

Exelon Nuclear -'Nuclear Fuels DOC ID: CGLR Clinton I Rev. 10' CLIC16 Core Operating Umits 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 Fuer, NEDE-2401 1-P-A US, May 2015 and U.S. Supplement NEDE-2401 1-P-A-21-US, May 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, "Clinton Power Station One Bypass Out of Service or Turbine Bypass System Out of Service Analysis - Final", July 2010.
3. Global Nuclear Fuel Document, 000N8865 Revision 2, "Supplemental Reload Licensing Report for Clinton Power Station Unit I Reload 15 Cycle 16, May 2015.
4. Global Nuclear Fuel Document, 000N8866 Revision 0, "Fuel Bundle Information Report for Clinton Power Station Unit I Reload 15 Cycle 16", March 2015.
5. General Electric Document, GE-NE-0000-0000-7456-O1P, "Option B Scram Times For Clinton Power Station", February 2002.
6. Exelon Transmittal of Design Information, TODI ES1400025 Revision 0, "Clinton Unit 1 Cycle 16 Final Resolved OPL-3 Parameters", November 21, 2014.
7. GE Hitachi Nuclear Energy Letter, CFL-EXN-LH1-12-059, "Affirmation of the Clinton Power Station Unit I MAPLHGR Reduction for Feedwater Riser Flow Asymmetry", April 25, 2012.
8. General Electric Document, GE-NE-0000-0026-1857-RI, "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-II)", May 2013.
10. Global Nuclear Fuel Document, NEDC-32868P, Rev. 5, "GE14 Compliance with Amendment 22 of NEDE-24011-P-A (GESTAR-Il)", May 2013.
11. GE Hitachi Nuclear Energy Report, 0000-01 57-4599-RO, "Evaluation of Loss of Stator Water Cooling for Clinton", March 2013.
12. Exelon Technical Evaluation, EC EVAL 399725, Rev. 1, "Determination of Conservative Clinton Power Station TCV Lift Curve and TBSOOS Power Level Restriction", May 2015.

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