ML103130080

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FitzPatrick - Core Operating Limits Report, Revision 25
ML103130080
Person / Time
Site: FitzPatrick Constellation icon.png
Issue date: 10/06/2010
From: Drews W
Entergy Nuclear Northeast, Entergy Nuclear Operations
To:
Office of Nuclear Reactor Regulation
References
JAFP-10-0145
Download: ML103130080 (27)
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Text

JAFP-1 0-0145 ENCLOSURE 2 Core Operating Limits Report Revision 25 (Non-proprietary Version)(26 Pages Including Contents)

JAFP-10-0145 Enclosure 2 Contents Core Operating Limits Report 25 Pages Entergy ENTERGY NUCLEAR OPERATIONS, INC.JAMES A. FITZPATRICK NUCLEAR POWER PLANT REPORT CORE OPERATING LIMITS REPORT REVISION 25 I APPROVED BY: William Drews REACTOR ENGINEERING SUPERVISOR DATE: ilaLI APPROVED BY: GENERAL MANAGER -PLANT OPERATIONS DATE:_____

NON-PROPRIETARY VERSION CORE OPERATING LIMITS REPORT CYCLE 20 REVISION RECORD-> Summary of Changes Rev. 25 Effective upon final approval Applicable for use during Cycle 20 Operation.

Revision issued to update this document for FitzPatrick Reload 19 Cycle 20 cycle dependent data.Changed MCPR Limits reporting format for = 0 and tr # 0 to Tables 8.1, 8.2, 8.3, and 8.4. Redundant information contained in Figures was removed.APLHGR Limits reporting format no longer uses figure format. Pertinent information is tabulated in Table 8. 5 LHGR Limits reporting is limited to tabulated format in Table 8.6. GNF2 Pellet exposure extended to 63.5 GWD/ST per Ref. 3.18. Redundant information contained in the exposure dependent LHGR limit figures was removed. Fig. 8. 3 rd decimal changed to 0.58 from 0.581.Two new.references added: ODYSY application to Licensing Stability calculation LTR (Ref. 3.10), and SER for Amendment 33 to GESTAR (Ref. 3.18)approving PRIME application for GNF2 thermal-mechanical limits.Update to cycle specific references.

Page re-numbering, re-formatting, tables and figures order and re-numbering triggered editorial changes all throughout this document.§7.4.1.2 note removed as no longer applicable because ARTS-MEOD fully implemented.

This revision record and summary added.Rev. No. 25 Page 2of 25 NON-PROPRIETARY VERSION CORE OPERATING LIMITS REPORT CYCLE 20 TABLE OF CONTENTS SECTION PAGE 1.0 PU R P O SE ......................................................................................................................

4 2.0 A PPLICA BILIT Y ...........................................................................................................

4 3.0 R E FE R E N C E S ..............................................................................................................

4 4.0 D EFIN ITIO N S ....................................................................................................

5 5.0 RESPON SIBILITIES

............................................................................

...................

6 6.0 SPECIAL INSTRUCTIONS/REQUIREMENTS

....................................................

6 7.0 PR O CE D U R E ...............................................................................................................

7 7.1 Operating Limit MCPR ..........................................................................

7 7.2 Average Planar Linear Heat Generation Rate (APLHGR) .....................

9 7.3 Linear Heat Generation Rate (LHGR) .......................................................

10 7.4 APRM Allowable Values (Digital Flow Cards) .....................................

11 7.5 RBM Upscale Rod Block Allowable Value ...........................................

12 7.6 Stability Option 1-D Exclusion Region and Buffer Zone ......................

12 8.0 TABLES AND FIGURES ........................................................................................

12 TABLE 8.1 MCPR Operating Limit For Incremental Cycle Core Average E xposure ...................................................................

....................

13 TABLE 8.2 MCPR Operating Limit for Incremental Cycle Core Average Exposure for Operation above 75% of Rated Thermal Power with Three Steam Lines in Service ...............................................

14 TABLE 8.3 MCPR Operating Limit for Operation with Turbine Bypass Valves Out of Service ...................................................................

15 TABLE 8.4 MCPR Operating Limit for Operation with Final Feedwater Temperature Reduction

................................................................

16 TABLE 8.5 Exposure Dependent APLHGR Limits ...........................

17 TABLE 8.6 Maximum LHGR .........................................................................

18 Figure 8.1 MCPR(F) Factor .............................................................................

19 Figure 8.2 K(P), OLMCPR(P)

Factor .............................................................

20 Figure 8.3 Flow-Dependent LHGR Multiplier, LHGRFAC(F)

.......................

21 Figure 8.4 Power-Dependent LHGR Multiplier, LHGRFAC(P)

.............

22 Figure 8.5 Stability Option 1-D Exclusion Region ............................................

23 Figure 8.6 Cycle 20 Loading Pattern by Bundle Design .................................

24 9.0 U SE R S G U ID E ............................................................................................................

25 Rev. No. 25 Page 3 of 25 NON-PROPRIETARY VERSION CORE OPERATING LIMITS REPORT CYCLE 20 1.0 PURPOSE This report provides the cycle-specific operating limits for Cycle 20 of the James A.FitzPatrick Nuclear Power Plant. The following limits are addressed:

  • Operating Limit Minimum Critical Power Ratio (MCPR)* Flow Dependent MCPR Limits* Average Planar Linear H-Ieat Generation Rate (APLHGR)* Linear Heat Generation Rate (LHGR)* Flow-Biased Average Power Range Monitor (APRM) and Rod Block Monitor (RBM)Allowable Values* Stability Option ID Exclusion Region 2.0 APPLICABILITY The plant shall be operated within the limits specified in this report. If any of these limits are exceeded, the corrective actions specified in the Technical Specifications shall be taken.

3.0 REFERENCES

3.1 EN-LI-113, Licensing Basis Document Change process 3.2 JAFNPP Technical Specifications.

,3.3 EC18500, Cycle 20 Core Reload 3.4 EN-DC-503, 3D Monicore New Cycle Update and Databank Maintenance.

3.5 Plant

Operation Up To 100% Power With One Steam Line Isolated, JAF-SE-96-035.

3.6 GE Report, J.A. FitzPatrick Nuclear Power Plant APRM/RBM/Technical Specifications

/Maximum Extended Operating Domain (ARTS/MEOD), NEDC-33087P, Revision 1, September 2005 3.7 General Electric Standard Application for Reload Fuel, NEDE-24011-P-A-16 3.8 GNF Report, Supplemental Reload Licensing Report for James A. FitzPatrick Reload 19 Cycle 20, 0000-0108-3718-SRLR, Revision 0, Class I, June, 2010. [EC23541, ECH-NE-10-00060 RO]3.9 "GNF2 Fuel Design Cycle-Independent Analyses For Entergy FitzPatrick", GE Report,, GEH- -0000-0074-2662-RI, June 2010. [EC23634, JAF-RPT-08-00013 Ri]3.10 Licensing Topical Report, ODYSY Application for Stability Licensing Calculations Including Option I-D and II Long Term Solutions, NEDE-33213P-A, April 2009 Rev. No. 25 Page 4 of 25 NON-PROPRIETARY VERSION CORE OPERATING LIMITS REPORT CYCLE 20 3.11 GE Letter, R. Kingston to P. Lemberg, Scram Time Versus Notch Positions for Option B, REK-E: 02-009, May 28, 2002 3.12 GE Report, James A. FitzPatrick Nuclear Power Plant Final Feedwater Temperature Reduction NEDC-33077, September 2002.3.13 JD-02-122, Final Feedwater Temperature Reduction Implementation.

3.14 GE Report, GE14 Fuel Design Cycle-Independent Analyses forJ. A. Fitzpatrick Nuclear Power Plant, GE-NE-0000-0002-1752-01P, Rev. 0, DRF 0000-0002-1752, September 2002.3.15 GNF Report, Fuel Bundle Information Report for James A. FitzPatrick Reload 19 Cycle 20, 0000-0108-3718-FBIR, Revision 0, June 2010. [EC23547, ECH-NE-10-00061 RO]3.16 JF-03-00402, ARTS/MEOD Phase 1 Implementation 3.17 JAF-RPT-MISC-04489, Rev.7, Power-Flow Map Report 3.18 "Final Safety Evaluation For Amendment 33 To Global Nuclear Fuel Topical Report NEDE-24011-P, "General Electric Standard Application For Reactor Fuel (GESTAR II)" (TAC NO. ME3525), Aug. 30, 2010 4.0 DEFINITIONS

4.1 Average

Planar Linear Heat Generation Rate (APLHGR): The APLHGR shall be applicable to a specific planar height and is equal to the sum of the heat generation rate per unit length of fuel rod for all the fuel rods in the specified assembly at the specified height divided by the number of fuel rods in the fuel assembly at the height.4.2 Linear Heat Generation Rate (LHGR): The LHGR shall be the heat generation rate per unit length of fuel rod. It is the integral of the heat flux over the heat transfer area associated with the unit length.4.3 Minimum critical power ratio (MCPR): The MCPR shall be the smallest critical power ratio (CPR) that exists in the core for each type of fuel. The CPR is that power in the assembly that is calculated by application of the appropriate correlation(s) to cause some point in the assembly to experience boiling transition, divided by the actual assembly operating power.4.4 Rated Recirculation Flow: That drive flow which produces a core flow of 77.0 x 106 lb/hr.Rev. No. 25 Page 5 of 25 NON-PROPRIETARY VERSION CORE OPERATING LIMITS REPORT CYCLE 20 5.0 RESPONSIBILITIES NOTE: See EN-LI-113 (Reference 3.1)5.1 Shift Manager: Assure that the reactor is operated within the limits described herein.5.2 Reactor Engineering Supervisor:

Assure that the limits described herein are properly installed in the 3D-Monicore databank used for thermal limit surveillance (Reference 3.4)6.0 SPECIAL INSTRUCTIONS/REQUIREMENTS Not Applicable Rev. No. 25 Page 6 of 25 NON-PROPRIETARY VERSION CORE OPERATING LIMITS REPORT CYCLE 20 7.0 PROCEDURE 7.1 Operating Limit MCPR During operation, with thermal power > 25% 0of rated thermal power (RTP), the Operating Limit MCPR shall be equal to or greater than the limits given below.7.1.1 Technical Specification LCO 3.2.2, Minimum Critical Power Ratio (MCPR)7.1.2 The Operating Limit MCPR shall be determined based on the following requirement:

7.1.2.1 The average scram time to notch position 36 shall be: T AVE <- B 7.1.2.2 The average scram time to notch position 36 is determined as follows: n SNiri i=1 TA VE n i=I WHERE: n = Number of surveillance tests performed to date in the cycle, Ni = Number of active rods measured in the surveillance i Average scram time to notch position 36 of all rods measured in surveillance test i.Rev. No. 25 Page 7 of 25 NON-PROPRIETARY VERSION CORE OPERATING LIMITS REPORT CYCLE 20 7.1.2.3 The adjusted analysis mean scram time is calculated as follows: 1/2 1-B(sec)=p~+1.65oa NI n INi-i=l WHERE:ýt = Mean of the distribution for the average scram insertion time to the dropout of notch position 36 = 0.830 sec.=Y Standard deviation of the distribution for average scram insertion time to the dropout of notch position 36 = 0.019 sec.N 1 The total number of active rods measured in Technical Specification SR 3.1.4.4.The number of rods to be scram tested and the test intervals are given in Technical Specification LCO 3.1.4, Control Rod Scram Times 7.1.3 When requirement of 7.1.2.1 is met, the Operating Limit MCPR shall not be less than that specified in Table8. 1, Table8.2, Table8._2, or Table8.4 as applicable for t -0.7.1.4 WHEN the requirement 7.1.2.1 is not met (i.e. 'UAVE > tB), THEN the Operating Limit MCPR values (as a function of'U) are given in Tables 8., 8.2, 8.2, or 8.4 as applicable.

('CAVE -TO (TA -- TB)WHERE: TAVE = The average scram time to notch position 36 as defined in 7.1.2.2.I CB = The adjusted analysis mean scram time as defined in 7.1.2.3.TA the scram time to notch position 36 as defined in Technical Specification Table 3.1.4-1.Rev. No. 25 Page 8 of 25 NON-PROPRIETARY VERSION CORE OPERATING LIMITS REPORT CYCLE 20 7.1.5 During single-loop operation, the Operating Limit MCPR shall be increased by 0.03.7.1.6 The Operating Limit MCPR is the greater of the flow and power dependent MCPR operating limits, MCPR(F) and MCPR(P).Operating Limit MCPR = MAX (MCPR(P), MCPR(F))The flow dependent MCPR operating limit, MCPR(F), is provided in Figure 8.1.For core thermal powers equal to or greater than 25%, MCPR (P) is the product of the rated Operating Limit MCPR presented in Tables 8.L1, 2 8.2, or 8.4 and the K (P) factor presented in Figure 8.2.7.2 Average Planar Linear Heat Generation Rate (APLHGR)7.2.1 Technical Specification LCO 3.2.1, Average Planar Linear Heat Generation Rate (APLHGR)7.2.2 During operation, with thermal power > 25% rated thermal power (RTP), the APLHGR shall be within the limits given in Table 8. 5 for the appropriate fuel type.7.2.3 During single loop operation, the APLHGR for each fuel type shall not exceed the values given in 7.2.2 above multiplied by the appropriate value (0.78 for GEI4 fuel and 0.85 for GNF2 fuel, per Ref. 3.8).Rev. No. 25 Page 9 of 25 NON-PROPRIETARY VERSION CORE OPERATING LIMITS REPORT CYCLE 20 7.3 Linear Heat Generation Rate (LHGR)7.3.1 Technical Specification LCO 3.2.3, Linear Heat Generation Rate (LHGR)7.3.2 During operation, with thermal power > 25% rated thermal power (RTP), the applicable limiting LHGR values for each fuel rod as a function of axial location and exposure shall be the smaller of the power and flow dependent LHGR limits multiplied by the applicable power and flow adjustment or the LHGR limit multiplied by 0.78 (for GE14) or 0.85 (for GNF2) when in single loop operation.

LHGR limit = MIN (LHGR (P), LHGR (F)).Power-dependent LHGR limit, LHGR (P), is the product of the LHGR power dependent LHGR limit adjustment factor, LHGRFAC (P), shown in Figure 8.4 and the LHGR,,d in Table 8.6.LHGR (P) = LHGRFAC(P) x LHGRStd The flow-dependent LHGR limit, LHGR (F), is the product of the LHGR flow dependent LHGR limit adjustment factor, LHGRFAC (F), shown in Figure 8.3 and the LHGRStd in Table 8.6.LHGR (F) = LHGRFAC(F) x LHGRStd Rev. No. 25 Page 10 of 25 NON-PROPRIETARY VERSION CORE OPERATING LIMITS REPORT CYCLE 20 7.4 APRM Allowable Values (Digital Flow Cards)7.4.1 APRM Flow Referenced Flux Scram Allowable Value (Run Mode)7.4.1.1 Technical Specifications:

LCO 3.3.1.1, Reactor Protection System (RPS) Instrumentation 7.4.1.2 When operating in Mode 1, the APRM Neutron Flux-High (Flow Biased)Allowable Value shall be for two loop operation:

S< (% RTP) = 0.38*W+61.0%

S_ (% RTP) = 1.15*W+42.0%

S_ (%.RTP) = 0.63*W+73.7%

S< (% RTP) = 117.00% (Clamp)for single loop operation:

S_ (% RTP) = 0.38*W+57.9%

S< (% RTP)= 1.15*W+32.8%

S5 (% RTP) = 0.58*W+61.3%/

S< (% RTP)= 117.00% (Clamp)0< W___ 24.7%24.7< W < 47.0%47.0< W < 68.7%W > 68.7%0< W 32.7%32.7< W -< 50.1%50.1< W -95.9%W > 95.9%WHERE: S = Allowable value in percent of rated thermal, power;W = Recirculation flow in percent of rated;7.4.2 APRM Neutron Flux-High (Flow Biased) Rod Block Allowable Value (Relocated to the Technical Requirements Manual)I Rev. No. 25 Page 11 of 25 NON-PROPRIETARY VERSION CORE OPERATING LIMITS REPORT CYCLE 20 7.5 RBM Upscale Rod Block Allowable Value 7.5.1 Technical Specification LCO 3.3.2.1, Control Rod Block Instrumentation 7.5.2 The RBM upscale rod block allowable value shall be: S <_ 0.66W + K for two loop operation; S _ 0.66W + K -0.66 AW for single loop operation; WHERE: r S rod block allowable value in percent of initial;W Loop flow in percent of rated K Any intercept value may be used because the RBM intercept value does not effect the MCPR Operating Limit and the RBM is not assumed to function to protect the Safety Limit MCPR.AW Difference between two loop and single lodp effective drive flow at the same core flow.NOTE: If K can be any value, then K -0.66AW can also be any value, and the allowable value adjustment for single loop operation is not necessary.

7.6 Stability

Option 1-D Exclusion Region and Buffer Zone.7.6.1 Technical Specification LCO 3.4.1, Recirculation Loops Operating 7.6.2 The reactor shall not be intentionally operated within the Exclusion Region given in Figure 8.5 when the SOLOMON Code is operable.7.6.3 The reactor shall not be intentionally operated within the Buffer Zone given in Figure 8.5 when the SOLOMON Code is inoperable.

8.0 TABLES

AND FIGURES 8.1 Following pages present Tables 8.1 through 8.6, and Figures 8.1 through 8.6. Exact tables and figures names are listed in the Table of Content on page 3.I I Rev. No. 25 Page 12 of 25 NON-PROPRIETARY VERSION CORE OPERATING LIMITS REPORT CYCLE 20 TABLE 8.1 MCPR Operating Limit For Incremental Cycle Core Average Exposure GNF2 (Reload 19) GNF2 (Reload 18) GEl4 BOC to MOC to BOC to MOCto BOC to MOC to MOC EOC MOC EOC MOC EOC=0 1.42 1.48 1.43 1.48 1.39 1.43>0.0 <0.1 1.43 1.49 1.43 1.49 1.40 1.45>0.1 <0.2 1.44 1.50 1.44 1.50 1.41 1.46>0.2 <0.3 1.45 1.51 1.45 1.51 1.42 1.48>0.3 <0.4 1.46 1.52 1.46 1.52 1.43 1.50>0.4 <0.5 1.47 1.53 1.47 1.53 1.45 1.52>0.5 <0.6 1.48 1.54 1.48 1.54 1.46 1.53>0.6 <0.7 1.49 1.55 1.49 1.55 1.47 1.55>0.7 _<0.8 1.50 1.56 1.50 1.56 1.48 1.57>0.8 0.9 1.51 1.57 1.51 1.57 1.49 1.58>0.9 1<1 1.52 1.58 1.52 1.58 1.50 1.60 Technical Specification LCO 3.2.2, Minimum Critical Power Ratio (MCPR)For single loop operation, these limits shall be increased as given in Section 7.1.5.The MCPR limits in this Table are subject to Power and Flow dependent adjustment per Section 7.1.6 NOTE: 1. When entering a new Exposure Range, check the current value of T to assure adjustment per Step 7.1.4 2. Applicable for any value of K, see Step 7.5.2 Rev. No. 25 Page 13 of 25 NON-PROPRIETARY VERSION CORE OPERATING LIMITS REPORT CYCLE 20 TABLE 8.2 MCPR Operating Limit for Incremental Cycle Core Average Exposure for Operation above 75% of Rated Thermal Power with Three Steam Lines in Service GNF2 GE14 BOC to MOC MOC to EOC BOC to MOC MOC to EOC= 0 1.44 1.50 1.41 1.45>0.0 _<0.1 1.45 1.51 1.42 1.47>0.1 <0.2 1.46 1.52 1.43 1.48>0.2 <0.3 1.47 1.53 1.44 1.50>0.3 _<0.4 1.48 1.54 1.45 1.52>0.4 <-0.5 1.49 1.55 1.47 1.54>0.5 <0.6 1.5 1.56 1.48 1.55>0.6 <0.7 1.51 1.57 1.49 1.57>0.7 <-0.8 1.52 1.58 1.50 1.59>0.8 <0.9 1.53 1.59 1.51 1.60>0.9 _<1 1.54 1.60 1.52 1.62 Technical Specification LCO 3.2.2, Minimum Critical Power Ratio (MCPR)For single loop operation, these limits shall be increased as given in Section 7.1.5.The MCPR limits in this Table are subject to Power and Flow dependent adjustment per Section 7.1.6 NOTE: 1. When entering a new Exposure Range, check the current value of t to assure adjustment per Step 7.1.4 2. Applicable for any value of K, see Step 7.5.2 Rev. No. 25 Page 14 of 25 NON-PROPRIETARY VERSION CORE OPERATING LIMITS REPORT CYCLE 20 TABLE 8.3 MCPR Operating Limit for Operation with Turbine Bypass Valves Out of Service GNF2 GE14 BOC to EOC BOC to EOC 0 1.51 1.47>0.0 <0.1 1.52 1.49>0.1 <0.2 1.53 1.50>0.2 <0.3 1.54 1.52>0.3 <0.4 1.55 1.54>0.4 <0.5 1.56 1.56>0.5 <0.6 1.57 1.57>0.6 <0.7 1.58 1.59>0.7 <0.8 1.59 1.61>0.8 _<0-9 1.60. 1.62>0.9 _<1 1.61 1.64 Technical Specification LCO 3.2.2, Minimum Critical Power Ratio (MCPR)Technical Specification LCO 3.7.6, Main Turbine Bypass System For single loop operation, these limits shall be increased as given-in Section 7.1.5.The MCPR limits in this Table are subject to Power and Flow dependent adjustment per Section 7.1.6 NOTE: 1. When entering a new Exposure Range, check the current value of'C to assure adjustment per Step 7.1.4 2. Applicable for any value of K, see Step 7.5.2 Rev. No. 25 Page 15 of 25 NON-PROPRIETARY VERSION CORE OPERATING LIMITS REPORT CYCLE 20 TABLE 8.4 MCPR Operating Limit for Operation with Final Feedwater Temperature Reduction GNF2 GE14 EOC EOC 0 1.48 1.43>0.0 <0.1 1.49 1.45>0.1 <0.2 1.50 1.46>0.2 <0.3 1.51 1.48>0.3 <0.4 1.52 1.50>0.4 <0.5 1.53 1.52>0.5 <0.6 1.54 1.53>0.6 <0.7 1.55 1.55>0.7 <0.8 1.56 1.57>0.8 -0.9 1.57 1.58>0.9 -<1 1.58 1.60 Technical Specification LCO 3.2.2, Minimum Critical Power Ratio (MCPR)For single loop operation, these limits shall be increased as given in Section 7.1.5.The MCPR limits in this Table are subject to Power and Flow dependent adjustment per Section 7.1.6 NOTE: 1. When entering a new Exposure Range, check the current value of 'T to assure adjustment per Step 7.1.4 2. Applicable for any value of K, see Step 7.5.2 MCPR Operating Limits in this table apply when at reduced feedwater temperature near end-of-cycle, see JD-02-122 (Reference 3.13) for further information.

Rev. No. 25 R Page 16 of 25 NON-PROPETARY VERSION CORE OPERATING LIMITS REPORT CYCLE 20 TABLE 8.5 Exposure Dependent APLHGR Limits I GE14 Fuel Types Average Planar APLHGR Limit Exposure GWd/ST kW/ft 0.00 12.82 14.51 12.82 19.13 12.82 57.61 8.00 63.50 5.00 GNF2 Fuel Types Average Planar APLHGR Limit Exposure GWd/ST kW/ft 0.00 13.78 13.24 13.78 17.52 13.78 60.78 7.50 63.50 6.69 Technical Specification LCO 3.2.1, Average Planar Linear Heat Generation Rate (APLHGR)For single loop operation these APLHGR values shall be multiplied by 0.85 for GNF2 fuel or 0.78 for GE14 fuel.Linearly interpolate for APLHGR at intermediate exposure.Rev. No. 25 Page 17 of 25 NON-PROPRIETARY VERSION CORE OPERATING LIMITS REPORT CYCLE 20 TABLE 8.6 Maximum LHGR Maximum LHGR -GE14 Peak Pellet Exposure, GWD/ST UO 2 LHGR Limit, kW/ft 0.00 13.40 14.51 13.40 57.61 8.00 63.50 5.00 Peak Pellet Exposure, GWd/ST Most Limiting Gadolinia LHGR Limit, kW/ft 0.00 12.26 12.28 12.26 55.00 7.32 60.84 4.57 Maximum LHGR -GNF2 Peak Pellet Exposure, GWD/ST UO 2 LHGR Limit, kW/ft Peak Pellet Exposure, GWd/ST Most Limiting Gadolinia LHGR Limit, kW/ft[II Technical Specification LCO 3.2.3, Linear Heat Generation Rate (LHGR)Design features of the fuel assemblies in the Cycle 20 core are provided in References 3.3, 3.15.LHGRsrd values in the above Table 8.6 are subject to Power and Flow dependent adjustments per Section 7.3 For single loop operation these LHGR values shall be multiplied by 0.85 (for GNF2 fuel) or 0.78 (for GE14)Linearly interpolate for LHGR at intermediate exposure Rev. No. 25 Page 18 of 25 NON CORE OPERATING LIMITS REPORT PROPRIETARY VERSION-CYCLE 20 Figure 8.1 MCPR(F) Factor 1.70 1.60 LL C, 1.50 1.40 w (D (D o 1.30 0 1.20 1.10 20 30 40 50 60 70 80 Core Flow (% rated)90 100 110 Technical Specification LCO 3.2.2, Minimum CriticalPower Ratio (MCPR)Reference 3.8 Rev. No. 25 Page 19 of 25 NON-PROPRIETARY VERSION CORE OPERATING LIMITS REPORT CYCLE 20 Figure 8.2 K(P), OLMCPR(P)

Factor 2.8 -Operating Limit MCPR (P) = K(P)

  • Operating Limit: ', MCPR(100)2.7 For P<25%: No Thermal Limits Monitoring Required, No 2.6 .limits specified 2.5 -. For 25%<P<P(Bypass), P(Bypass)=29%,
  • OLMCPR(P)=2.31+0.0125*(29%-P), Flow<_60%2.4 OLMCPR(P)=2.58+0.0275*(29%-P)'

Flow>60%2.3 For P-P(Bypass)

  • K(P)=1.390+0.0118*(40%-P), 29%-<P<40%

U)2.240 P<%K(P)=1.189+0.0101*(60%-P), 40%-<P<60%

K(P)=1.056+0.00532*(85%-P), 60%<P<85%AC1 2 ...K(P)=1.00+0.00373*(100%-P), 85%<P<100%

V 2 .0 .------------

1 .7 ...............

.1.5 -... ..........

1.4-" 1.3 -........ ----- ............

..........

-.....................

....................

............

1.2 1 .4 --. ... ..1.0 20 30 40 .50 60 70 80 90 100 110 Power (%.rated)See Table 8.1, 8.22 8.3,and Table 8.4 for Operating Limit.MCPR(1 00)Technical Specification LCO 3.2.2, Minimum Critical Power Ratio (MCPR)Reference 3.8 C-Rev. No. 25 Page 20 of 25 NON-PROPRIETARY VERSION CORE OPERATING LIMITS REPORT CYCLE 20 Figure 8.3 Flow-Dependent LHGR Multiplier, LHGRFAC(F) 1.10 1. 00- ii_____ ---U-0.90 0.80 U-l:. 0.70 0 o 06.1.0 o 0.60 ,-¢0.50 0.40-t-- F 7 x x __________________

+ F'000ýLHGR(F)=LHGRFACf*LHGRstd Max Flow= 112%Flow LHGRFACf 30% 0.626 85% 1.000 110% 1.000 0.30+ -i F F I I I I 30 40 50 60 70 80 90 100 Flow, %rated 110 See Table 8.6 for LHGRsrn value Reference 3.9 I Rev. No. 25 Page 21 of 25 NON-PROPRIETARY VERSION CORE OPERATING LIMITS REPORT CYCLE 20 Figure 8.4 Power-Dependent LHGR Multiplier, LHGRFAC(P) 1.1 -__-_1.0 I I I I 0.9 I i i i I I 0.8 U .0 .7 -. .. ------ --- .........

--.. .....For P<25%, No Thermal Limits Required 0. -Pbypass =29% Pbwer I I for <29%P, >60%F KLHGRFACp

= 0.531+0.0045*(P-29) 0.5 ---- -----05 I I for <29%P, <60%F I LHGRFACp =0.58 0 .4 .. .... .... ............04for 29%<P51O00%

LHGRFACp = 1.000+0.00528*(P-100)0.3 , , 20 30 40 50 60 70 80 90 100 Power, % rated See Table 8.6 for LHGRsTD values Reference 3.9 Rev. No. 25 Page 22 of 25 S NON-PROPRETARY VERSION CORE OPERATING LIMITS REPORT CYCLE 20 Figure 8.5 Stability Option 1-D Exclusion Region 110 100 90 80 0 (L.70 60 50 40 30 20 20 25 30 35 40 45 50 55 Flow, % rated 60 65 70 See References 3.17 and 3.8 for details The Cycle 20 Exclusion Region boundary is applicable for Cycle 20 exposure up to 15613 MWD/ST Rev. No. 25 Page 23 of 25 NON-PROPRIETARY VERSION CORE OPERATING LIMITS REPORT CYCLE 20 Figure 8.6 Cycle 20 Loading Pattern by Bundle Design North 52 443 32 11 [E [E 11 _1[ 011 1_f -24El EllW[M EIJ el LKI E&22 M ts M FM M M M 1MR1 rn M R I]14 Q F AF.T -E T7~86[_2 _ 15D El rr i[ [r 119r RD [EB 4= Ei+IM E]tIM FAT! IEIIE 1 3 5 7 9 1113 15 17 19212325 27 293133 35 37 39414345 47 4951 Fuel Type AGE14-PIODNAkB4O2-IC600J4G5.0/102)0-100T-150-T6-2-905 G=G-NF2-P10DG2B394-13GZ-100T2-150-T&-3077 (Cycle, 19)(Cycle 19) H=GNF2-P10DIG2B37S-16GZ-100T2-150-T&-3299 (Cycle 20)B=GE14-P1ODNXAB405-16GZ-100T-l30-T6-2.906 (Cycle 19) IlGNF2-PIODG2B380-1dGZ-1OOT2-4-150-T6-32'98 (Cycle 2Q)C=GNF2--P10DG2B377-13G2-100T2-150-ýTO-3073 (Cycle 19) J=G.NF2-P10DG2B4D4-12GZ-100T2-150-TO-3297 (Cycle 20)D=GNF2-P10DG2B379-14GZ-10012-150.TO-3;074 (Cycle 19) K=GNF2-PlODG2B39Oý-I4GZ-IOOTh2150-T6-3300 (Cycle-20)

E=GNF2-P10DG2B396-15GZ-100T2-150-T6-3075 (Cycle 19)F=GNF2-PIGDG2B407-6G6.0/e6G5iO-100T2-150-TO-3076 (Cycle 19) _________________

Rev. No. 25 Page 24 of 25 NON-PROPRIETARY VERSION CORE OPERATING LIMITS REPORT CYCLE 20 9.0 USERS GUIDE The COLR defines thermal limits for the various operating conditions expected during the cycle. At the start of the cycle the 3D-Monicore databank limits are set for;* Cycle exposure range of BOC to MOC20* = 0* Dual recirculation pump operation* Four steam line operation, and* Normal Feedwater Temperature The following is a table that offers a check to assure the correct limits are applied when operating states or conditions change.Procedure Change in Operating State Change in Limits Reference Cycle Exposure = EOC20 -2.946 GWD/ST EN-DC-503 OLMCPR changes to EOC values at cycle See Table 8.1 for # 0 for change in transition to exposure of 11.495 GWD/ST. Databank will MCPR. EOC limits will use 11.000 GWD/ST to account for occur uncertainties, automatically Scram Time Test Results such that t 0 Use new T and see Table 8.1 8.2, RAP-7.4.1 Option BWlimits for. OLMCPR must be 8.3,and Table 8.4.interpolated with Option A limits Single Loop Operation Increase MCPR Limits by 0.03, or The SLMCPR increases by 0.03 and, change acceptance criterion in ST-40D therefore OLMCPR limits increase by3 0.03. (Step 8.2.19) to 0.97.LJ-TGR and MAPLHGR are reduced by a Verify that 3D-Monicore has ST-40D multiplier in SLO. recognized the idle recirculation loop and is applying the SLO LHGR and MAPLHGR multipliers of 0.78 for GE14 and 0.85 for GNF2.Three Steam Line Operation (3SL) Increase OLMCPR according to Table 8.2. None Operation with Turbine Bypass Valves Out-of-Service Increase OLMCPR according to Table OLMCPR values increase, no LHGR change 8.3. None required Operation under Final Feedwater Temperature Reduction Apply OLMCPR according to Table 8.4. None Rev. No. 25 Page 25 of 25

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