Text

Issuance of the Core Operating Limits Report for Reload 20, Cycle 21, Revision 8
	ML15296A034
Person / Time
Site:	Peach Bottom
Issue date:	10/23/2015
From:	Massaro M; Exelon Generation Co
To:	; Document Control Desk, Office of Nuclear Reactor Regulation
References
	CCN: 15-81
	Download: ML15296A034 (25)
	v • d • e

October 23, 2015 U.S. Nuclear Regulatory Commission Attention: Document Control Desk Washington DC 20555-0001

Subject:

Peach Bottom Atomic Power Station, Unit 3 Renewed Facility Operating License No. DPR-56 NRC Docket No. 50-278 Issuance of the Core Operating Limits Report for Reload 20, Cycle 21, Revision 8 TS 5.6.5.d Enclosed is a copy of Revision 8 of the Core Operating Limits Report (COLR) for Peach Bottom Atomic Power Station (PBAPS) Unit 3 for Reload 20, Cycle 21. Revision 8 of this report incorporates the revised cycle specific parameters resulting from the new core configuration as a result of the PBAPS Unit 3 refueling outage.

This COLR is being submitted to the NRC as required by the PBAPS, Unit 3 Technical Specifications (TS)

Section 5.6.5.d.

If you have any questions concerning this letter, please contact Dave Foss at (717) 456-4311.

Michael J. Massaro Site Vice President Peach Bottom Atomic Power Station CCN: 15-81 Attachment Unit 3 Core Operating Limits Report for Reload 20, Cycle 21, Revision 8 cc:

Regional Administrator, Region I, USNRC (without attachments)

USNRC Senior Resident Inspector, PBAPS (without attachments)

Project Manager-PBAPS, USNRC (with attachments)

R. R. Janati, Pennsylvania Bureau of Radiation Protection (without attachments)

S. T. Gray, State of Maryland (without attachments)

ATTACHMENT Core Operating Limits Report for Reload 20, Cycle 21, Revision 8

/

Exelon Nuclear - Nuclear Fuell P3C2 I Core Operating Limits Report COLR PEACH BOTTOM 3 Rev. 8 Page 1 of23 CORE OPE.RATING LIMITS REPORT FOR PEACH BOTTOM ATOMIC POWER STATION UNIT 3 RELOAD 20, CYCLE 21 (This is a Complete Re-write)

Prepared By:------------

B. Lambert Prepared By: _____

llJ_~_-_'f._yt,JL_

B. Miller

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?<dE~.

1'.eactor ngmeenng Reviewed By:

ReviewedBy: ___ <C&

___._.;;:_~------

Independent Review By:

Station Qualified Reviewer:

Engineering Safety Analysis 9/2912015 Date: __

9/29/2015 Date: __

Date: ~1 bO~ S Date: 9/30/15 Date:

9/30/15 D

10/5/15 ate: __

Exelon Nuclear - Nuclear Fuels P3C21 Core Operating Limits Report Table of Contents 1.0 Terms and Definitions 2.0 General Information 3.0 MAPLHGR Limits 4.0 MCPRLimits 5.0 Linear Heat Generation Rate Limits 6.0 Rod Block Monitor Setpoints 7.0 Turbine Bypass Valve Parameters 8.0 EOC Recirculation Pump Trip (EOC-RPT) Operability COLR PEACH BOTTOM 3 Rev. 8 Page 2of23 Page 4

5 6

7 11 13 14 15 9.0 Stability Protection Oscillation Power Range Monitor (OPRM) 16 10.0 Asymmetric Feedwater Temperature Operation (AFTO) 17 11.0 Modes of Operation 21 12.0 Methodology 22 13.0 References 22

Exelon Nuclear - Nuclear Fuels P3C2 l Core Operating Limits Report List of Tables Table 3-1 MAPLHGR Versus Average Planar Exposure Table 3-2 MAPLHGR Single Loop Operation (SLO) Multiplier Table 4-1 Operating Limit Minimum Critical Power Ratio COLR PEACH BOTTOM 3 Rev. 8 Page 3 of23 Page 6

6 8

Table 4-2 Power Dependent MCPR(P) Limit Adjustments and Multipliers 9

Table 4-3 Flow Dependent MCPR Limits MCPR(F)

Table 4-4 SLO Flow Dependent MCPR Limits MCPR(F)

Table 5-1 Linear Heat Generation Rate Limits - U02 rods Table 5-2 Linear Heat Generation Rate Limits - Gad rods Table 5-3 Power Dependent LHGR Multiplier LHGRF AC(P)

Table 5-4 Flow Dependent LHGR Multiplier LHGRF AC(F)

Table 6-1 Rod Block Monitor Setpoints Table 7-1 Turbine Bypass System Response Time Table 7-2 Minimum Required Bypass Valves to Maintain System Operability Table 9-1 OPRM PBDA Trip Settings 10 10 11 11 12 12 13 14 14 16 Table 9-2 OPRM PBDA Trip Settings - SLO 16 Table 10-1 AFTO Thermal Limit Penalties 17 Table 10-2 AFTO Power Dependent LHGR Multiplier LHGRF AC(P) 20F < FWT DELTA:::; 55F 18 Table 10-3 AFTO Flow Dependent LHGR Multiplier LHGRF AC(F) 20F < FWT DELTA:::; 55F 18 Table 10-4 AFTO Operating Limit Minimum Critical Power Ratio 20F < FWT DELTA:::; 55F 19 Table 10-5 AFTO Power Dependent MCPR Limit Adjustments and Multipliers 20 MCPR(P) 20F < FWT DELTA$ 55F Table 10-6 AFTO Flow Dependent MCPR Limits MCPR(F) 20F < FWT DELTA:::; 55F 20 Table 10-7 AFTO MAPLHGR Reduction Factor 21 Table 11-1 Modes of Operation 21 Table 11-2 Additional Equipment Out of Service Modes of Operation 21

Exelon Nuclear - Nuclear Fuels P3C2 I Core Operating Limits Report COLR PEACH BOTTOM 3 Rev. 8 Page4 of23 1.0 Terms and Definitions AFTO AFTOLFWH ARTS BASE BOC DTSP EOC EOOS EOR FFWTR FWHOOS FWT HTSP ICF ITSP LHGR LHGRFAC(F)

LHGRFAC(P)

LTSP MAPLHGR MCPR MCPR(F)

MCPR(P)

MELLLA MSIVOOS OLM CPR OPRMPBDA PLUOOS PROOS PR/PLUOOS RPTOOS RWE SLM CPR SLO TB SOOS TCV!TSVOOS Asymmetric Feedwater Temperature Operation Asymmetric Feedwater Temperature Operation Loss-of-Feedwater Heating APRM and RBM Technical Specification Analysis Defines two (2) loop operation with at least seven turbine bypass valves in service, the reactor recirculation pump trip system in service, the power load unbalance device in service, and both pressure regulators in service.

Beginning Of Cycle Rod Block Monitor Downscale Trip Setpoint End of Cycle Equipment Out of Service. An analyzed option that assumes certain equipment to be non-operational End of Rated. The cycle exposure at which reactor power is equal to 100% (3951 MW th) with recirculation system flow equal to 100%, all control rods fully withdrawn, all feedwater heating in service and equilibrium Xenon.

Final Feedwater Temperature Reduction Feedwater Heaters Out of Service Feedwater Temperature Rod Block Monitor High Trip Setpoint Increased Core Flow Rod Block Monitor Intermediate Trip Setpoint Linear Heat Generation Rate ARTS LHGR thermal limit flow dependent adjustments and multipliers ARTS LHGR thermal limit power dependent adjustments and multipliers Rod Block Monitor Low Trip Setpoint Maximum Average Planar Linear Heat Generation Rate Minimum Critical Power Ratio ARTS MCPR thermal limit flow dependent adjustments and multipliers ARTS MCPR thermal limit power dependent adjustments and multipliers Maximum Extended Load Line Limit Analysis Main Steam Isolation Valve Out of Service Operating Limit Minimum Critical Power Ratio Oscillation Power Range Monitor Period Based Detection Algorithm Power Load Unbalance Out of Service Pressure Regulator Out of Service Pressure Regulator Out of Service and/or Power Load Unbalance Out of Service Recirculation Pump Trip Out of Service Rod Withdrawal Error Safety Limit Minimum Critical Power Ratio Single Loop Operation Turbine Bypass System Out of Service Turbine Control Valve!Turbine Stop Valve Out of Service

Exelon Nuclear - Nuclear Fuels P3C2 I Core Operating Limits Report 2.0 General Information COLR PEACH BOTTOM 3 Rev. 8 Page 5 of23 This report provides the following cycle-specific parameter limits for Peach Bottom Atomic Power Station Unit 3 CYCLE 21(RELOAD20):

Maximum Average Planar Linear Heat Generation Rate (MAPLHGR)

Single Loop Operation (SLO) MAPLHGR multipliers Operating Limit Minimum Critical Power Ratio (OLMCPR)

ARTS MCPR thermal limit adjustments and multipliers Single Loop Operation (SLO) MCPR adjustment Linear Heat Generation Rate (LHGR)

ARTS LHGR thermal limit multipliers Single Loop Operation (SLO) LHGR multipliers Rod Block Monitor (RBM) Analytical Limits, Allowable Values and MCPR Limits Turbine Bypass Valve Parameters EOC Recirculation Pump Trip (EOC-RPT) Parameters PR/PLUOOS thermal limits Dual Loop Stability Protection - Oscillation Power Range Monitor (OPRM) Trip Setpoints Single Loop Stability Protection - Oscillation Power Range Monitor (OPRM) Trip Setpoints Asymmetric Feedwater Temperature Operation (AFTO) thermal limit penalties These values have been determined using NRC-approved methodology and are established such that all applicable limits of the plant safety analysis are met.

This report provides cycle-specific Operating Limit MCPR, LHGR, MAPLHGR thermal limits, and related information for the following conditions:

All points in the operating region of the power/flow map including Maximum Extended Load Line Limit (MELLL) down to 99% ofrated core flow during full power (3951 MWt) operation Increased Core Flow (ICF), up to 110% of rated core flow End-of-Cycle Power Coastdown to a minimum power level of 40%

Feedwater Heaters Out of Service (FWHOOS) to 55° F temperature reduction Final Feedwater Temperature Reduction (FFWTR) between End-of-Rated (EOR) and End-of-Cycle (EOC) to 90° F temperature reduction (4th and 5th stage FFWTR)

Asymmetric Feedwater Temperature Operation (AFTO)

AR TS provides for power-and flow-dependent thermal limit adjustments and multipliers that allow for a more reliable administration of the MCPR and LHGR thermal limits. The OLMCPR is determined by the cycle-specific reload analyses in Reference 2. Rated LHGR values are obtained from the bundle-specific thermal-mechanical analysis. Supporting documentation for the AR TS-based limits is provided in Reference 2. The Allowable Values documented in Reference 5 for feedwater temperature as a function of thermal power for both FWHOOS and FFWTR are specified in the appropriate Peach Bottom procedures.

Also note that the following description of MAPLHGR, LHGR and MCPR limits pertain to NON - AFTO conditions. A separate description of AFTO limits and their associated ARTS tables are located in Section 10.

Preparation of this report was performed in accordance with Exelon Nuclear procedures. This report is provided to the NRC in accordance with Technical Specification 5.6.5 of Reference 1 and contains all thermal limit parameters related to the implementation of the ARTS Improvement Program and Maximum Extended Load Line Limit Analysis (ARTS/MELLLA) for Peach Bottom Unit 3 Cycle 21.

The "BASE" thermal limit values shown in tables are for normal two (2) loop operation with at least seven turbine bypass valves in service, the reactor recirculation pump trip system in service, the power load unbalance device in service, and both pressure regulators in service.

Exelon Nuclear - Nuclear Fuels P3C2 l Core Operating Limits Report 3.0 MAPLHGR LIMITS 3.1 Technical Specification Section 3.2.1, 3.3.4.2, 3.4.1and3.7.6 3.2 Description COLR PEACH BOTTOM 3 Rev. 8 Page 6 of23 The MAPLHGR limits (kW/ft) obtained from the emergency core cooling system (ECCS) analysis are provided in Table 3-1. The MAPLHGR limits comprise a given fuel type as a function of average planar exposure. The MAPLHGR tables are used when hand calculations are required. All MAPLHGR values for GNF2 as a function of axial location and average planar exposure shall be less than or equal to the applicable MAPLHGR limits for GNF2 fuel and lattice type. These MAPLHGR limits are specified in Reference 2 and the process computer databank. The SLO MAPLHGR multiplier is provided in Table 3-2 per Reference 2 and must be applied to the Table 3-1 limits when operating in SLO.

The impact of AFTO on MAPLHGR is addressed in Section 10.

TABLE 3-1 MAPLHGR Versus Average Planar Exposure (Reference 2)

Average Planar Exposure MAPLHGR Limit (GWD/ST)

(kW/ft) 0.0 13.78 17.52 13.78 60.78 7.50 63.50 6.69 TABLE3-2 MAPLHGR Single Loop Operation (SLO) Multiplier (Reference 2)

SLO Multiplier 0.73

Exelon Nuclear - Nuclear Fuels P3C2 I Core Operating Limits Report 4.0 MCPR LIMITS 4.1 Technical Specification Section 2.1.1.2, 3.2.2, 3.3.4.2, 3.4.1and3.7.6 4.2 Description COLR PEACH BOTTOM 3 Rev. 8 Page 7 of23 The Operating Limit MCPR (OLMCPR) for GNF2 fuel is provided in Tables 4-1and4-2. These values are determined by the cycle-specific fuel reload analyses in Reference 2. Control rod scram time verification is required as per Technical Specification 3.1.4, "Control Rod Scram Times". Tau, a measure of scram time performance to notch position 36 throughout the cycle, is determined based on the cumulative scram time test results. The calculation of Tau shall be performed in accordance with site procedures. Linear interpolation shall be used to calculate the OLM CPR value if Tau is between 0.0 (Tau Option B) and 1.0 (Tau Option A).

Separate OLMCPR values are presented in Table 4-1 for the following conditions:

TBS In-Service (per section 7.0), RPT In-Service (per section 8.0), PLU/PR In-Service, and maximum FFWTR of 90 °F ( a.k.a. "BASE")

TBS Out-of-Service (per section 7.0), RPT In-Service (per section 8.0), PLU/PR In-Service, and maximum FFWTR of 90 °F

TBS In-Service (per section 7.0), RPT In-Service (per section 8.0), PLU/PR Out-of-Service, and maximum FFWTR of 90°F

TBS In-Service (per section 7.0), RPT Out-of-Service (per section 8.0), PLU/PR In-Service, and maximum FFWTR of 90 °F The ARTS-based power-dependent MCPR limits are provided in Table 4-2. Table 4-2 is valid for a maximum temperature reduction of90 °F for FFWTR operation. The flow-dependent MCPR limits are provided in Tables 4-3 and 4-4. Table 4-3 is valid for dual loop operating conditions with symmetric feedwater temperature operation and Table 4-4 is valid for single loop operating conditions with symmetric feedwater temperature operation. The impact of AFTO on MCPR is addressed in Section 10. For PR/PLUOOS + TBSOOS and PR/PLUOOS + RPTOOS conditions, the limits are listed in Section 10, these values are bounding for non-AFTO conditions.

Exelon Nuclear - Nuclear Fuels P3C2 I Core Operating Limits Report TABLE 4-1 COLR PEACH BOTTOM 3 Rev. 8 Page 8 of23 Operating Limit Minimum Critical Power Ratio (Reference 2)

SCRAM Cycle Exposure Time

<EOR-25~-

II EOOS Combination Option°>

d/~T

'"I B

1.35 1.39 BASE A

1.43 1.47 B

1.42 1.42 BASE SL0<2l A

1.46 1.50 B

1.40 1.44 RPTOOS A

1.57 1.61 B

1.43 1.47 RPTOOS SL0<2>

A 1.60 1.64 B

1.35 1.39 PR/PLUOOS A

1.43 1.47 B

1.42 1.42 PR/PLUOOS SL0<2>

A 1.46 1.50 B

1.38 1.41 TB SOOS A

1.47 1.50 B

1.42 1.44 TB SOOS SLO <2>

A 1.50 l.53 (1) When Tau does not equal 0 or 1, use linear interpolation.

(2) For single-loop operation, the MCPR operating limit is 0.03 greater than the analyzed limiting two loop value. However a minimum value of 1.42 is required to obtain an OLMCPR limit set by the Single Loop Operation Recirculation Pump Seizure Event (Reference 2).

Exelon Nuclear - Nuclear Fuels P3C2 l Core Operating Limits Report TABLE 4-2 COLR PEACH BOTTOM 3 Rev. 8 Page 9 of23 Power Dependent MCPR(P) Limit Adjustments and Multipliers (Symmetric Feedwater Heating)

(Reference 2)

Core Core Thermal Power (% of rated)

EOOS Combination Flow(%

0 23

<26.7

?.26.7 40 55 65 85 100 of rated) Operating Limit MCPR Operating Limit MCPR Multiplier, Kp

S 60 2.56 2.56 2.49 Base 1.352 1.352 1.317 1.131 1.082 1.000

>60 2.86 2.86 2.71

S 60 2.59 2.59 2.52 Base SLO 1.352 1.352 1.317 1.131 1.082 1.000

> 60 2.89 2.89 2.74

S 60 2.56 2.56 2.49 RPTOOS 1.352 1.352 1.317 1.131 1.082 1.000

>60 2.86 2.86 2.71

S 60 2.59 2.59 2.52 RPTOOSSLO

>60 2.89 2.89 2.74 1.352 1.352 1.317 1.131 1.082 1.000

S 60 2.56 2.56 2.49 PR/PLUOOS 1.392 1.352 1.317 1.210 1.147 1.000

>60 2.86 2.86 2.71

S 60 2.59 2.59 2.52 PR/PLUOOS SLO 1.392 1.352 1.317 1.210 1.147 1.000

> 60 2.89 2.89 2.74

S 60 3.48 3.48 3.11 TB SOOS 1.659 1.479 1.373 1.155 1.082 1.000

>60 3.97 3.97 3.62

S 60 3.51 3.51 3.14 TBSOOSSLO 1.659 1.479 1.373 1.155 1.082 1.000

>60 4.00 4.00 3.65

Exelon Nuclear - Nuclear Fuels P3C2 I Core Operating Limits Report TABLE4-3 COLR PEACH BOTTOM 3 Rev. 8 Page 10of23 Flow Dependent MCPR Limits MCPR(F)

(Symmetric Feedwater Heating) eference 2 MCPR(F)

Limit

.25 TABLE4-4 SLO Flow Dependent MCPR Limits MCPR(F)

(Symmetric Feedwater Heating) eference 2 Core Flow MCPR(F)

(% rated)

Limit

0.

1.70 1.53 1.25 1.25

Exelon Nuclear - Nuclear Fuels P3C2 l Core Operating Limits Report COLR PEACH BOTTOM 3 Rev. 8 Page 11of23 5.0 LINEAR HEAT GENERATION RATE LIMITS 5.1 Technical Specification Section 3.2.3, 3.3.4.2, 3.4.1 and 3.7.6 5.2 Description The LHGR values for GNF2 fuel type are provided in Tables 5-1and5-2. The ARTS-based LHGR power-dependent multipliers are provided in Table 5-3. Table 5-3 is valid for a maximum temperature reduction of 90° F for FFWTR operation. The flow-dependent multipliers are provided in Table 5-4 as a function of the number of recirculation loops in operation. The SLO LHGR multiplier is 0.73 and is accounted for in Table 5-4. The power-and flow-dependent LHGR multipliers were obtained from Reference 2. The impact of AFTO on LHGR is addressed in Section 10. For PRJPLUOOS + TBSOOS and PRJPLUOOS +

RPTOOS conditions, the limits are listed in Section 10, these values are bounding for non-AFTO conditions.

TABLE 5-1 Linear Heat Generation Rate Limits - U02 rods (References 4 and 11)

Fuel Type LHGRLimit GNF2 See Appendix B of Reference 4 TABLE 5-2 Linear Heat Generation Rate Limits - Gad rods (References 4 and 11)

Fuel Type LHGRLimit GNF2 C<

~-

~

Exelon Nuclear - Nuclear Fuels P3C2 l Core Operating Limits Report COLR PEACH BOTTOM 3 Rev. 8 Page 12of23 EOOS Combination Base Base SLO RPTOOS RPTOOSSLO PR/PLUOOS PR/PLUOOS SLO TB SOOS TBSOOSSLO TABLE5-3 Power Dependent LHGR Multiplier LHGRFAC(P)

(Symmetric Feedwater Heating)

(Reference 2)

Core Thermal Power (% of rated)

Core Flow 0

23

<26.7

~26.7 40 55

(%of rated)

LHGRFAC(P) Multiplier

60 0.508 0.508 0.522 0.748 0.756

> 60 0.508 0.508 0.522

60 0.508 0.508 0.522 0.748 0.756

>60 0.508 0.508 0.522

60 0.508 0.508 0.522 0.748 0.756

> 60 0.508 0.508 0.522

60 0.508 0.508 0.522 0.748 0.756

>60 0.508 0.508 0.522

60 0.508 0.508 0.522 0.620 0.696

> 60 0.508 0.508 0.522

60 0.508 0.508 0.522

0.620 0.696

>60 0.508 0.508 0.522

60 0.397 0.397 0.442 0.635 0.655

>60 0.397 0.397 0.417

60 0.397 0.397 0.442 0.635 0.655

>60 0.397 0.397 0.417 TABLE5-4 Flow Dependent LHGR Multiplier LHGRFAC(F)

(Symmetric Feedwater Heating)

(Reference 2)

Core Flow (% of rated) 0.771 0.771 0.771 0.771 0.751 0.751 0.714 0.714 EOOS Combination 0

30 33.6 70 80 LHGRFAC(F) Multiplier Dual Loop 0.506 0.706 0.730 0.973 1.000 Single Loop 0.506 0.706 0.730 0.730 0.730 65 85 0.817 0.959 0.817 0.959 0.817 0.959 0.817 0.959 0.817 0.959 0.817 0.959 0.817 0.930 0.817 0.930 110 1.000 0.730 100 1.000 1.000 1.000 1.000 1.000 1.000 1.000 1.000

Exelon Nuclear - Nuclear Fuels P3C21 Core Operating Limits Report 6.0 ROD BLOCK MONITOR SETPOINTS 6.1 Technical Specification Section 3.3.2.1 6.2 Description COLR PEACH BOTTOM 3 Rev. 8 Page 13of23 The RBM power-biased Analytical Limits, Allowable Values and MCPR Limits are provided in Table 6-1 with supporting documentation in References 2 and 9.

TABLE 6-1 Rod Block Monitor Setpoints (References 2 and 9)

Power Level Analytical Limit0 l Allowable Value0 >

MCPRLimit LTSP 123.0%

121.2%

< 1.70 <2l

<l.40<3l ITSP 118.0%

116.2%

< 1.70 <2>

< 1.40 <3l HTSP 113.2%

111.4%

< 1.70 <2l

< 1.40 <3>

INOP NIA NIA

< 1.70 <2l

< 1.40 (3)

(1) These setpoints (with RBM filter time constant between 0.1 seconds and 0.55 seconds) are based on a cycle-specific rated RWE MCPR limit which is less than or equal to the minimum cycle OLMCPR based on other events (see COLR References 2 and 9).

(2) This is the MCPR limit (

THERMAL POWER is required to be OPERABLE see COLR Reference 2

.4% and < 90%) below which the RBM is TS Table 3.3.2.1-1).

(3) This is the MCPR limit (given THERMAL POWER is > 90%) below which the RBM is required to be OPERABLE (see COLR Reference 2 and TS Table 3.3~2.1-1).

Exelon Nuclear - Nuclear Fuels P3C2 l Core Operating Limits Report 7.0 TURBINE BYPASS VAL VE PARAMETERS 7.1 Technical Specification Section 3.7.6 7.2 Description COLR PEACH BOTTOM 3 Rev. 8 Page 14of23 The operability requirements for the steam bypass system are governed by Technical Specification 3.7.6. If the requirements cannot be met, the appropriate power and flow dependent limits for Turbine Bypass System Out-of-Service (TBSOOS) must be used. Additionally, the OLMCPR for TBSOOS must be applied. Table 7-1 includes the Turbine Bypass Valve response time parameters. The minimum number of bypass valves to maintain system operability is provided in Table 7-2 per Reference 14.

TABLE 7-1 Turbine Bypass System Response Time (Reference 14)

Maximum delay time before start of bypass valve opening following initial turbine inlet valve movement0 l Maximum time after initial turbine inlet valve movement0 l for bypass valve position to reach 80% of full flow (includes the above delay time) 0.10 sec 0.30 sec (I)

First movement of any TSV QI any TCV QI generation of the tmbine bypass valve flow signal (whichever occurs first)

TABLE 7-2 Minimum Required Bypass Valves To Maintain System Operability (Reference 14)

Reactor Power No. of Valves in Service p 2: 23%

7

Exelon Nuclear - Nuclear Fuels P3C2 I Core Operating Limits Report COLR PEACH BOTTOM 3 Rev. 8 Page 15of23 8.0 EOC RECIRCULATION PUMP TRIP (EOC-RPT) OPERABILITY 8.1 Technical Specification Section 3.3.4.2 8.2 Description The operability requirements for the EOC Recirculation Pump Trip are governed by Technical Specification 3.3.4.2. If the requirements cannot be met, the appropriate power and flow dependent limits for EOC Recirculation Pump Trip Out Of Service (RPTOOS) must be used.

Additionally, the OLM CPR for RPTOOS must be applied.

A total RPT response time of 0.175 seconds is assumed in the safety analysis and is defined as the time from when the turbine valves (turbine control valve or turbine stop valve) start to close until complete arc suppression of the EOC-RPT circuit breakers. Reference 7 provides the basis for the RPT response time.

Exelon Nuclear - Nuclear Fuels P3C21 Core Operating Limits Report COLR PEACH BOTTOM 3 Rev. 8 Page 16 of23 9.0 STABILITY PROTECTION OSCILLATION POWER RANGE MONITOR (OPRM) 9.1 Technical Specification Section 3.3.1.1, Table 3.3.1.1-1Function2.f 9.2 Description The CYCLE 21 OPRM Period Based Detection Algorithm (PBDA) Trip Settings are provided in Table 9-1 and 9-2. These values are based on the cycle specific analysis documented in Reference 2.

The PBDA is the only OPRM setting credited in the safety analysis as documented in the licensing basis for the OPRM system, Reference 13. The OPRM Growth Rate Algorithm (GRA) and Amplitude Based Algorithm (ABA) trip settings for dual loop and single loop can be found in the Power Range Neutron Monitoring Configuration Control Documents (SPID's) G-080-VC-l 74 through 177 (Unit-3).

TABLE 9-1 OPRM PBDA Trip Settings (Valid for All Conditions)

(Reference 2)

PBDA Trip Amplitude Corresponding Maximum Confirmation Count Trip Setting 1.10 TABLE9-2 OPRM PBDA Trip Settings - SLOOl (Valid For SLO Conditions Only)

(Reference 2) 13 PBDA Trip Amplitude Corresponding Maximum Confirmation Count Trip Setting (1) The standard two prior to restarting 1.18 17 in Table 9-1 must be implemented

Exelon Nuclear - Nuclear Fuels P3C2 l Core Operating Limits Report COLR PEACH BOTTOM 3 Rev. 8 Page 17 of23 10.0 ASYMMETRIC FEEDWATER TEMPERATURE OPERATION (AFTO)

Asymmetric feedwater heating (resulting from removing a heater string, or individual feedwater heaters, from operation) is the result of the specific configuration of the feedwater lines at Peach Bottom. A reduction in heating in either the 'A' or the 'C' heater strings will result in a temperature mismatch between the feedwater flows entering the opposite sides of the reactor vessel. This temperature mismatch may result in errors in the thermal limit values calculated by the core monitoring system. Thermal limit values for all conditions and events are impacted by these errors excluding SLO conditions. The P3C21 COLR Rev. 8 is the first COLR to no longer require implementation of SLO AFTO penalty files for this unit. The station no longer requires SLO AFTO files or penalties due to a 3D MONICORE upgrade required for EPU operation.

Asymmetric feedwater temperature operation (AFTO) is defined as operation in a feedwater heater/string configuration that results in a specified threshold difference as described in Reference 10. To simplify the implementation of the AFTO limits, only the maximum AFTO penalties indicated in Table 10-1 will be implemented when the threshold asymmetry temperature (temperature above which a penalty is required) is exceeded. This will minimize the number of AFTO thermal limit tables in the COLR and core monitoring system.

40F < FWT DELTA:::; SSF 30F < FWT DELTA:::; 40F 20F < FWT DELTA:::; 30F OF< FWT DELTA:::; 20F TABLE 10-1 AFTO Thermal Limit Penalties (Asymmetric Feedwater Heating)

(Reference 10)

MFLCPR 3%

2%

No Penalty LHGRLIMITS MFLPD/MAPRAT 4%

3%

2%

No Penalty The ARTS-based LHGR power-dependent multipliers for AFTO operation are provided in Table 10-2. The flow-dependent multipliers for AFTO in DLO are provided in Table 10-3. The power-and flow-dependent LHGR multipliers were obtained from Reference 2 and were adjusted with the appropriate penalties displayed in Table 10-1 as per Reference 10. PR/PLUOOS + TBSOOS and PR/PLUOOS + RPTOOS values were obtained by taking the most limiting OLMCPR values of the two EOOS conditions, these values are bounding for non-AFTO conditions. The maximum feedwater temperature difference allowed without a thermal limit penalty is 20 °F. Once the temperature difference exceeds 20 °F the maximum penalties from Table 10-1 are applied to the thermal limits. Additionally, no LHGR penalties are required for asymmetric feedwater temperature option while in SLO as previously discussed.

Exelon Nuclear - Nuclear Fuels P3C2 l Core Operating Limits Report COLR PEACH BOTTOM 3 Rev. 8 Page 18 of23 TABLE 10-2 AFTO Power Dependent LHGR Multiplier LHGRFAC(P) 20F < FWT DELTA:::; 55F (Asymmetric Feedwater Heating)

(References 2 and 10)

Core Core Thermal Power (% of rated)

EOOS Combination Flow 0

23

<26.7 2:26.7 40 55 65

(%of rated)

LHGRF AC(P) Multiplier

S60 0.488 0.488 0.501 Base 0.718 0.726 0.740 0.784

>60 0.488 0.488 0.501

60 0.488 0.488 0.501 RPTOOS 0.718 0.726 0.740 0.784

>60 0.488 0.488 0.501

60 0.488 0.488 0.501 PR/PLUOOS 0.595 0.668 0.721 0.784

>60 0.488 0.488 0.501

60 0.381 0.381 0.424 TB SOOS 0.610 0.629 0.685 0.784

> 60 0.381 0.381 0.400

60 0.381 0.381 0.424 PR/PLUOOS + TBSOOS 0.595 0.629 0.685 0.784

>60 0.381 0.381 0.400

60 0.488 0.488 0.501 PR/PLUOOS + RPTOOS 0.595 0.668 0.721 0.784

>6" A

A r.r...

0.488 0.501 TABLE 10-3 AFTO Flow Dependent LHGR Multiplier LHGRF AC(F) 20F < FWT DEL TA:::; 55F (Asymmetric Feedwater Heating)

(References 2 and 10)

Core Flow (% of rated)

EOOS Combination 0

I 30 I

33.60 I

70 I

80 I

LHGRFAC(F) Multiplier Dual Loop 0.486 I 0.678 I

0.701 I

0.934 l 0.960 I

85 0.921 0.921 0.921 0.893 0.893 0.921 110 o.~rA 100 0.960 0.960 0.960 0.960 0.960 0.960

Exelon Nuclear - Nuclear Fuels P3C2 l Core Operating Limits Report MCPRLIMITS COLR PEACH BOTTOM 3 Rev. 8 Page 19of23 The OLMCPRs during asymmetric feedwater temperature operation with a feedwater temperature difference greater than 20 °P are provided in Table 10-4. The ARTS-based power-dependent MCPR limits for use during AFTO conditions are provided in Table 10-5. The flow-dependent MCPR limits for AFTO are provided in Table 10-6.

The power and flow-dependent OLMCPR curves were obtained from Reference 2 and were adjusted with a 3% penalty for feedwater temperature difference greater than 20 °P as displayed in Table 10-1 as per Reference 10. PR/PLUOOS + TBSOOS and PR/PLUOOS + RPTOOS values were obtained by taking the most limiting OLMCPR values of the two EOOS conditions, these values are bounding for non-AFTO conditions. No MCPR penalties are required for asymmetric temperature differentials less than or equal to 20 °P. Additionally, no MCPR penalties are required for asymmetric feedwater temperature option while in SLO as previously discussed.

TABLE 10-4 AFTO Operating Limit Minimum Critical Power Ratio 20F < FWT DELTA ::S 55F (Asymmetric Feedwater Heating)

References 2 and 10)

SCRAM Cycle Exposure

~I Time

<EOR-2523 ;::EOR-25 EOOS Combination Option(t)

MWd/ST MWd/ST BASE B

1.39 1.43 A

1.47 1.51 RPTOOS B

1.44 1.48 A

1.62 1.66 PRIPLUOOS B

1.39 1.43 A

1.47 1.51 TB SOOS B

1.42 1.45 A

1.51 1.55 PR/PLUOOS + TBSOOS B

1.42 1.45 A

NIA NIA PRIPLUOOS + RPTOOS B

1.44 1.48 A

NIA NIA (1) When Tau does not equal 0 or 1, use linear interpolation.

Exelon Nuclear - Nuclear Fuels P3C2 l Core Operating Limits Report TABLE 10-5 COLR PEACH BOTTOM 3 Rev. 8 Page 20 of23 AFTO Power Dependent MCPR Limit Adjustments And Multipliers MCPR(P) 20F < FWT DEL TA

55F (Asymmetric Feedwater Heating)

(References 2 and 10)

Core Core Thermal Power (% of rated)

EOOS Combination Flow

(%of 0

23

<26.7

?:26.7 40 55 65 85 100 rated) Operating Limit MCPR Operating Limit MCPR Multiplier, Kp

60 2.64 2.64 2.56 Base 1.352 1.352 1.317 1.131

> 60 2.95 2.95 2.79

60 2.64 2.64 2.56 RPTOOS 1.352 1.352 1.317 1.131

>60 2.95 2.95 2.79 PR/PLUOOS

60 2.64 2.64 2.56 1.392 1.352 1.317 1.210

>60 2.95 2.95 2.79

60 3.58 3.58 3.20 TB SOOS 1.659 1.479 1.373 1.155

>60 4.09 4.09 3.73 PR/PLUOOS + TBSOOS

60 3.58 3.58 3.20 1.659 1.479 1.373 1.210

> 60 4.09 4.09 3.73

60 2.64 2.64 2.56 PR/PLUOOS + RPTOOS 1.392 1.352 1.317 1.210

> 60 2.95 2.95 2.79 TABLE 10-6 AFTO Flow Dependent MCPR Limits MCPR(F) 20F < FWT DELTA ::S 55F (BOC to EOC)(Asymmetric Feedwater Heating)

(References 2 and 10)

Flow MCPR(F)

(%rated)

Limit 0.0 1.75 30.0

.5 9.0 110.0 1.2 1.082 1.000 1.082 1.000 1.147 1.000 1.082 1.000 1.147 1.000 1.147 1.000

Exelon Nuclear - Nuclear Fuels P3C2 l Core Operating Limits Report COLR PEACH BOTTOM 3 Rev. 8 Page 21of23 MAPLHGR LIMITS An appropriate penalty must be applied to MAPLHGR limits under asymmetric feedwater temperature operation (AFTO) for varying temperature differentials as displayed in Table 10-1 as per Reference 10. No MAPLHGR penalties are required for asymmetric feedwater temperature option while in SLO as previously discussed.

TABLE 10-7 AFTO MAPLHGR Reduction Factor (Asymmetric Feedwater Heating)

(References 2 and 10)

AFTO Reduction Factor 20F<FWTDELTA:'.S55F I 0.960 11.0 MODES OF OPERATION EOOS 0ptions1 Base, Option A or B Base SLO, Option A or B TBSOOS, Option A or B TBSOOS SLO, Option A or B RPTOOS, Option A or B RPTOOS SLO, Option A or B PLUOOS, Option A or B PLUOOS SLO, Option A or B PROOS, Option A or B PROOS SLO, Option A or B TABLE 11-1 Modes of Operation (Reference 2)

PR/PLUOOS and TBSOOS, Option B PR/PLUOOS and RPTOOS, Option B TBSOOS and RPTOOS, Option A or B TBSOOS and RPTOOS SLO, Option A or B TABLE 11-2 Supported Operating Rei:don2 Yes Yes Yes Yes Yes Yes Yes Yes Yes Yes Yes Yes No No Additional Equipment Out of Service Modes of Operation EOOS TCV/TSVOOS (controlled via station procedures)

MSIVOOS (controlled via station procedures)

AFTO LFWH (controlled via station procedures) 1 Modes of operation with thermal limit sets in the COLR 2 Operating Region refers to operation on the Power to Flow map with or without FFWTR or AFTO

Exelon Nuclear - Nuclear Fuels P3C2 l Core Operating Limits Report 12.0 METHODOLOGY COLR PEACH BOTTOM 3 Rev. 8 Page 22 of23 The analytical methods used in determining the core operating limits have been previously reviewed and approved by the NRC, specifically those described in the following documents:

1. "General Electric Standard Application for Reactor Fuel", NEDE-24011-P-A-21, May 2015 and U.S.

Supplement NEDE-24011-P-A-21-US, May 2015.

2. "Maximum Extended Load Line Limit and ARTS Improvement Program Analyses for Peach Bottom Atomic Power Station Unit 2 and 3, NEDC-32162P, Revision 2, March 1995.

3. "Reactor Stability Detect and Suppress Solutions Licensing Basis Methodology for Reload Applications", NED0-32465-A, Revision 0, August 1996.

13.0 REFERENCES

1. "Technical Specifications for Peach Bottom Atomic Power Station Unit 3," Docket No. 50-278, Appendix A to License No. DPR-56.

2. Global Nuclear Fuel Document "Supplemental Reload Licensing Report for Peach Bottom Unit 3, Reload 20, Cycle 21 Extended Power Uprate (EPU)," GNF Document No. 001N3876, Revision 0, July 2015.

3. Global Nuclear Fuel Document "General Electric Standard Application for Reactor Fuel," NEDE-24011-P-A-21, May 2015 and U.S. Supplement NEDE-24011-P-A-21-US, May 2015.

4. Global Nuclear Fuel Document NEDC-33270P Rev. 5, "GNF2 Advantage Generic Compliance with NEDE-24011-P-A (GESTAR II)," May 2013.

5. General Electric Hitachi Document 001N2494-RO, "Peach Bottom EPU Evaluation of Feedwater Temperature vs. Reactor Power for Feedwater Temperature Conditions of Nominal Rated, FWHOOS (Nominal -55°F) and FFWTR (Nominal -90°F), July 2014. This document is searchable in Exelon EDMS under document number "PEAM-EPU-1 Rev. OOA."

6. Not Used

7. PECO Calculation PE-0173, "Determination of Total Time Required to Initiate the Trip Signal to the EOC-RPT Circuit Breakers Trip Coils and to Complete the Recirculation Pump Trip, Rev. 1 dated 12/22/98.

8. NotUsed.

9. PECO Calculation PE-0251, Revision 2A, "PRNMS Setpoint Calculation," dated 10/19/14.

10. General Electric Hitachi Document 001N6733-Rl, "Final Evaluation Report Exelon Nuclear Generating Company LLC, Peach Bottom Units 2 & 3, MELLLA+, Asymmetric Feedwater Temperature Operation for EPU/MELLLA+," Revision 1, September 2014. This document is searchable in Exelon EDMS under document number "PEAM-EPU-68 Rev. l."

Exelon Nuclear - Nuclear Fuels P3C2 l Core Operating Limits Report COLR PEACH BOTTOM 3 Rev. 8 Page 23 of23

11. Global Nuclear Fuel Document 002N8938, Revision 0, "Fuel Bundle Information Report for Peach Bottom Unit 3 Reload 20 Cycle 21 Extended Power Uprate (EPU)/Maximum Extended Load Line Limit Analysis Plus (MELLLA+) and Extended Power Uprate (EPU)/Maximum Extended Load Line Limit Analysis (MELLLA)," July 2015.

12. Not Used

13. General Electric Document NED0-32465-A, "Reactor Stability Detect and Suppress Solutions Licensing Basis Methodology for Reload Applications," August 1996.

14. Exelon TODI ENSAF ID# ES1500001, Rev. 0, "Final Resolved OPL-3 Parameters for Peach Bottom Unit 3 Cycle 21: EPU/MELLLA+," February 17, 2015.